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Sample records for mov inservice test

  1. Optimized periodic verification testing blended risk and performance-based MOV inservice test program an application of ASME code case OMN-1

    Energy Technology Data Exchange (ETDEWEB)

    Sellers, C.; Fleming, K.; Bidwell, D.; Forbes, P. [and others

    1996-12-01

    This paper presents an application of ASME Code Case OMN-1 to the GL 89-10 Program at the South Texas Project Electric Generating Station (STPEGS). Code Case OMN-1 provides guidance for a performance-based MOV inservice test program that can be used for periodic verification testing and allows consideration of risk insights. Blended probabilistic and deterministic evaluation techniques were used to establish inservice test strategies including both test methods and test frequency. Described in the paper are the methods and criteria for establishing MOV safety significance based on the STPEGS probabilistic safety assessment, deterministic considerations of MOV performance characteristics and performance margins, the expert panel evaluation process, and the development of inservice test strategies. Test strategies include a mix of dynamic and static testing as well as MOV exercising.

  2. Optimized periodic verification testing blended risk and performance-based MOV inservice test program an application of ASME code case OMN-1

    International Nuclear Information System (INIS)

    Sellers, C.; Fleming, K.; Bidwell, D.; Forbes, P.

    1996-01-01

    This paper presents an application of ASME Code Case OMN-1 to the GL 89-10 Program at the South Texas Project Electric Generating Station (STPEGS). Code Case OMN-1 provides guidance for a performance-based MOV inservice test program that can be used for periodic verification testing and allows consideration of risk insights. Blended probabilistic and deterministic evaluation techniques were used to establish inservice test strategies including both test methods and test frequency. Described in the paper are the methods and criteria for establishing MOV safety significance based on the STPEGS probabilistic safety assessment, deterministic considerations of MOV performance characteristics and performance margins, the expert panel evaluation process, and the development of inservice test strategies. Test strategies include a mix of dynamic and static testing as well as MOV exercising

  3. Integrated software tool automates MOV diagnosis

    International Nuclear Information System (INIS)

    Joshi, B.D.; Upadhyaya, B.R.

    1996-01-01

    This article reports that researchers at the University of Tennessee have developed digital signal processing software that takes the guesswork out of motor current signature analysis (MCSA). The federal testing regulations for motor-operated valves (MOV) used in nuclear power plants have recently come under critical scrutiny by the Nuclear Regulatory Commission (NRC) and the American Society of Mechanical Engineers (ASME). New ASME testing specifications mandate that all valves performing a safety function are to be tested -- not just ASME Code 1, 2 and 3 valves. The NRC will likely endorse the ASME regulations in the near future. Because of these changes, several utility companies have voluntarily expanded the scope of their in-service testing programs for MOVs, in spite of the additional expense

  4. OM Code Requirements For MOVs -- OMN-1 and Appendix III

    Energy Technology Data Exchange (ETDEWEB)

    Kevin G. DeWall

    2011-08-01

    The purpose or scope of the ASME OM Code is to establish the requirements for pre-service and in-service testing of nuclear power plant components to assess their operational readiness. For MOVs this includes those that perform a specific function in shutting down a reactor to the safe shutdown condition, maintaining the safe shutdown condition, and mitigating the consequences of an accident. This paper will present a brief history of industry and regulatory activities related to MOVs and the development of Code requirements to address weaknesses in earlier versions of the OM Code. The paper will discuss the MOV requirements contained in the 2009 version of ASME OM Code, specifically Mandatory Appendix III and OMN-1, Revision 1.

  5. OM Code Requirements For MOVs -- OMN-1 and Appendix III

    International Nuclear Information System (INIS)

    DeWall, Kevin G.

    2011-01-01

    The purpose or scope of the ASME OM Code is to establish the requirements for pre-service and in-service testing of nuclear power plant components to assess their operational readiness. For MOVs this includes those that perform a specific function in shutting down a reactor to the safe shutdown condition, maintaining the safe shutdown condition, and mitigating the consequences of an accident. This paper will present a brief history of industry and regulatory activities related to MOVs and the development of Code requirements to address weaknesses in earlier versions of the OM Code. The paper will discuss the MOV requirements contained in the 2009 version of ASME OM Code, specifically Mandatory Appendix III and OMN-1, Revision 1.

  6. Risk evaluation for motor operated valves in an Inservice Testing Program at a PWR nuclear power plant in Taiwan

    International Nuclear Information System (INIS)

    Li, Y.C.; Chen, K.T.; Su, Y.L.; Ting, K.; Chien, F.T.; Li, G.D.; Huang, S.H.

    2012-01-01

    Safety related valves such as Motor Operated Valves (MOV), Air Operated Valves (AOV) or Check Valves (CV) play an important role in nuclear power plant. Functioning of these valves mainly aim at emergency reactivity control, post-accident residue heat removal, post-accident radioactivity removal and containment isolation when a design basis accident occurred. In order to maintain these valves under operable conditions, an Inservice Testing Program (IST) is defined for routine testing tasks based on the ASME Boiler and Pressure Vessel Code section XI code requirements. Risk based Inservice Testing Programs have been studied and developed extensively in the nuclear energy industry since the 1990s. Risk Based evaluations of IST can bring positive advantages to the licensee such as identifying the vulnerability of the system, reducing unnecessary testing burden, concentrating testing resources on the critical pass oriented valves and saving plant’s personnel dose exposure. This risk evaluation is incorporated with quantitative and qualitative analyses to the Motor Operated Valves under current Inservice Testing Program for PWR nuclear power plant in Taiwan. With the outcome of the risk classifications for the safety related MOVs through numerical or deterministic analyses, a risk based testing frequency relief is suggested to demonstrate the benefits received from the risk based Inservice Testing Program. The goal made of this study, it could be as a reference and cornerstone for the licensee to perform overall scope Risk-Informed Inservice Testing Program (RI-IST) evaluation by referring relevant methodologies established in this study.

  7. A Methodology for Evaluation of Inservice Test Intervals for Pumps and Motor-Operated Valves

    International Nuclear Information System (INIS)

    Cox, D.F.; Haynes, H.D.; McElhaney, K.L.; Otaduy, P.J.; Staunton, R.H.; Vesely, W.E.

    1999-01-01

    Recent nuclear industry reevaluation of component inservice testing (IST) requirements is resulting in requests for IST interval extensions and changes to traditional IST programs. To evaluate these requests, long-term component performance and the methods for mitigating degradation need to be understood. Determining the appropriate IST intervals, along with component testing, monitoring, trending, and maintenance effects, has become necessary. This study provides guidelines to support the evaluation of IST intervals for pumps and motor-operated valves (MOVs). It presents specific engineering information pertinent to the performance and monitoring/testing of pumps and MOVs, provides an analytical methodology for assessing the bounding effects of aging on component margin behavior, and identifies basic elements of an overall program to help ensure component operability. Guidance for assessing probabilistic methods and the risk importance and safety consequences of the performance of pumps and MOVs has not been specifically included within the scope of this report, but these elements may be included in licensee change requests

  8. An application of risk-informed evaluation on MOVs and AOVs for Taiwan BWR-type nuclear power plants

    International Nuclear Information System (INIS)

    Ting, K.; Chen, K.T.; Li, Y.C.; Hwang, S.H.; Chien, F.T.; Kang, J.C.

    2008-01-01

    Implementing a risk-informed inservice testing (RI-IST) program provides a good aspect to the nuclear power plant licensee as an alternating program in the current ASME Section XI and 10 CFR 50.55a relevant testing programs. RI-IST concentrates testing resources on highly significant components, reduces excess testing burden, increases plant's availability, decreases dose rate on the plant's staff and also reduces cost on plant's operation and maintenance under nuclear safety expectations. Furthermore, RI-IST also gives a feature on prospective licensing change basis to a nuclear power plant's licensee. This study will focus on safety-related and PRA-molded motor-operated valves (MOVs) and air-operated valves (AOVs) under the inservice testing program in boiling water reactor (BWR)-type nuclear power plant. As MOVs and AOVs have crucial safety functions throughout the nuclear power plant's safety systems, the steady operation and performance of MOVs and AOVs will definitely ensure that the nuclear power plant operates under safety expectations; therefore, this is the key reason to implement risk-informed evaluation for MOVs and AOVs in this study and being able to provide the safety significance classification for MOVs and AOVs under the current IST program to the plant's management. As a pilot study of RI-IST, the methodology of qualitative assessment will incorporate with probabilistic risk assessment (PRA) analyzing MOVs' and AOVs' safety significance within the current PRA model. The evaluating result will then classify its safety significance into a high-safety significant component (HSSC) and a low-safety significant component (LSSC) for MOVs and AOVs based on relevant regulatory criteria. With this initiating achievement, it can provide a cornerstone for further studies on the other types of valves and pumps in RI-IST program and also provide a valuable reference as proposing license change to the licensee

  9. EPRI MOV performance prediction program

    International Nuclear Information System (INIS)

    Hosler, J.F.; Damerell, P.S.; Eidson, M.G.; Estep, N.E.

    1994-01-01

    An overview of the EPRI Motor-Operated Valve (MOV) Performance Prediction Program is presented. The objectives of this Program are to better understand the factors affecting the performance of MOVs and to develop and validate methodologies to predict MOV performance. The Program involves valve analytical modeling, separate-effects testing to refine the models, and flow-loop and in-plant MOV testing to provide a basis for model validation. The ultimate product of the Program is an MOV Performance Prediction Methodology applicable to common gate, globe, and butterfly valves. The methodology predicts thrust and torque requirements at design-basis flow and differential pressure conditions, assesses the potential for gate valve internal damage, and provides test methods to quantify potential for gate valve internal damage, and provides test methods to quantify potential variations in actuator output thrust with loading condition. Key findings and their potential impact on MOV design and engineering application are summarized

  10. MOV reliability evaluation and periodic verification scheduling

    Energy Technology Data Exchange (ETDEWEB)

    Bunte, B.D.

    1996-12-01

    The purpose of this paper is to establish a periodic verification testing schedule based on the expected long term reliability of gate or globe motor operated valves (MOVs). The methodology in this position paper determines the nominal (best estimate) design margin for any MOV based on the best available information pertaining to the MOVs design requirements, design parameters, existing hardware design, and present setup. The uncertainty in this margin is then determined using statistical means. By comparing the nominal margin to the uncertainty, the reliability of the MOV is estimated. The methodology is appropriate for evaluating the reliability of MOVs in the GL 89-10 program. It may be used following periodic testing to evaluate and trend MOV performance and reliability. It may also be used to evaluate the impact of proposed modifications and maintenance activities such as packing adjustments. In addition, it may be used to assess the impact of new information of a generic nature which impacts safety related MOVs.

  11. MOV reliability evaluation and periodic verification scheduling

    International Nuclear Information System (INIS)

    Bunte, B.D.

    1996-01-01

    The purpose of this paper is to establish a periodic verification testing schedule based on the expected long term reliability of gate or globe motor operated valves (MOVs). The methodology in this position paper determines the nominal (best estimate) design margin for any MOV based on the best available information pertaining to the MOVs design requirements, design parameters, existing hardware design, and present setup. The uncertainty in this margin is then determined using statistical means. By comparing the nominal margin to the uncertainty, the reliability of the MOV is estimated. The methodology is appropriate for evaluating the reliability of MOVs in the GL 89-10 program. It may be used following periodic testing to evaluate and trend MOV performance and reliability. It may also be used to evaluate the impact of proposed modifications and maintenance activities such as packing adjustments. In addition, it may be used to assess the impact of new information of a generic nature which impacts safety related MOVs

  12. Detecting MOV stem to stem-nut lubricant degradation by reviewing MOV open-quotes seating timeclose quotes

    International Nuclear Information System (INIS)

    Loweth, W.A.

    1996-01-01

    The objective is to describe a methodology, suitable for IST Programs, that obtains sufficient data to assess and trend the overall condition of AC and DC MOVs. Using existing diagnostic test equipment, recording the time from Hard Seat Contact to the Torque Switch Trip point (TST), open-quote Seating Time (msec)close quotes, can provide a means to quickly detect for signs of lubricant degradation in the interface between the stem and stem-nut for MOVs. Obtaining and trending the open-quote Seating Time close-quote parameter can be easily accomplished using the sensors which provide motor current, torque or thrust. From the initial baseline test to subsequent tests, it is the change in time between Hard Seat Contact to Torque Switch Trip point that is utilized to monitor changes in the coefficient of friction between the stem and stem-nut. While many Licensees have begun their MOV Periodic Verification Programs, obtaining the open-quotes Seating Timeclose quotes during Refueling Outages and comparing the results from subsequent outages can be an input to the justification for changing the MOV baseline test frequency

  13. Detecting MOV stem to stem-nut lubricant degradation by reviewing MOV {open_quotes}seating time{close_quotes}

    Energy Technology Data Exchange (ETDEWEB)

    Loweth, W.A.

    1996-12-01

    The objective is to describe a methodology, suitable for IST Programs, that obtains sufficient data to assess and trend the overall condition of AC and DC MOVs. Using existing diagnostic test equipment, recording the time from Hard Seat Contact to the Torque Switch Trip point (TST), {open_quote}Seating Time (msec){close_quotes}, can provide a means to quickly detect for signs of lubricant degradation in the interface between the stem and stem-nut for MOVs. Obtaining and trending the {open_quote}Seating Time{close_quote} parameter can be easily accomplished using the sensors which provide motor current, torque or thrust. From the initial baseline test to subsequent tests, it is the change in time between Hard Seat Contact to Torque Switch Trip point that is utilized to monitor changes in the coefficient of friction between the stem and stem-nut. While many Licensees have begun their MOV Periodic Verification Programs, obtaining the {open_quotes}Seating Time{close_quotes} during Refueling Outages and comparing the results from subsequent outages can be an input to the justification for changing the MOV baseline test frequency.

  14. Elements of a total MOV maintenance program

    International Nuclear Information System (INIS)

    Lavallee, W.L.

    1989-01-01

    Establishing a good preventive and predictive maintenance program for motor-operated valves (MOVs) is an especially challenging task for nuclear power plants. Because of the sheer number of MOVs involved, all with somewhat different characteristics and requirements, and the extremely critical functions that some of the MOVs perform, the maintenance program quickly becomes a major exercise in coordination. This paper outlines a three-phase approach to achieving a comprehensive MOV maintenance program. It is based on experience in assisting nuclear plants with their MOV programs and encountering many of the pitfalls that can hamper these programs. The three phases include up-front engineering preparation, field diagnostic testing, and maintenance follow-up and trending. Each of these phases is discussed, and a flowchart describing the individual elements of each phase is provided

  15. Parametric Study for MOV Performance Improvement Using PPM Program

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seungho; Seon, Juhyoung; Han, Bongsub [SOOSAN INDUSTRIES, Seoul (Korea, Republic of)

    2016-10-15

    Nuclear power plants mainly use Air Operated Valve(hereinafter referred to as AOV) and Motor Operator Valve(hereinafter referred to as MOV) for protecting system, blocking and controlling flow. Field test(static, dynamic test) results and performance prediction program are used to evaluate if MOV currently installed on nuclear power plants has the operational performance. The improvement of operating performance for Flexible Gate valve was confirmed on changing input variables of performance program(PPM). here are several methods through reviewing design basis, changes operating procedures and maintenance work of stem(or packing, etc.) to improve operating performance of MOV generally installed in the nuclear power plants. This study verified the changes of the MOV operating performance through the improvement of stem and hydraulic parts(seat, guide etc.). Especially, MOV operating performance was much greater improved when the Disk Seat Angle was decreasing. Generally, improvement work to minimize friction of seat, disk and guide is limited and dynamic diagnostic testing has to be performed with change in valve factor for improvement of hydraulic parts.

  16. MOV refurbishment program cuts costs, meets requirements

    International Nuclear Information System (INIS)

    Lengyel, G.J.

    1991-01-01

    This paper reports that a motor operated valve (MOV) rebuild program at Peach Bottom Atomic power station began in October, 1986 with what is known internally as Modification (MOD) 1915. The Engineering the Research Department developed this modification to address requirements in NRC Bulletin 85-03. The MOD consisted of As found/As left testing of MOVs in the HPCI (high pressure coolant injection) and RCIC (reactor core isolation cooling) systems; six minor motor operator enhancements to facilitate maintenance and testing, and to increase reliability, and installation of a data acquisition network to support differential pressure testing of a select number of valves in Unit 2. Twenty-four valves were involved. Modification plans incorporated the work into the outage that was scheduled for December, 1986 to February, 1987. The plans took into account other preventive and corrective MOV maintenance tasks to be performed by the Maintenance Department. In addition, modifications of control circuits to satisfy separation criteria for Appendix R had to be integrated into the schedule. To facilitate testing, adjustments to the standard test methods under the Permits and Blocking System were necessary. The normal method of testing a piece of equipment after maintenance was to clear or temporarily clear the permit (red tag) and have a plant operator operate the equipment for the test group. This method for setting up the testing an MOV was considered unacceptable because it could occupy a plant operator for an entire shaft or longer

  17. Special considerations for testing rising rotating stem MOVs

    International Nuclear Information System (INIS)

    Moffa, A.

    1992-01-01

    Rising stem gate and globe valves have one plane of motion: linear. The stem is either pushed or pulled into position. For rising and rotating stems however, there are two planes of motion: linear and rotational. The stem is twisted in addition to being pushed or pulled into position. Typical motor operated valve (MOV) sizing equations account only for the linear requirements of the valve to open or close. Theoretical calculations performed for a two-dimensional system predict that in the running load region, rotational torque requirements far exceed the linear requirements. To validate the theoretical model, torque testing of rising rotating stem valves was preformed, using Liberty Technologies Valve Operation Test and Evaluation System (VOTES). Theoretical and empirical data have produced a new perspective for operational requirements and a guideline for testing rising rotating stem valves

  18. Preventive maintenance program of motorized operated valves (MOV) at Cernavoda NPP

    International Nuclear Information System (INIS)

    Groza, M.; Moldoveanu, Edy

    2001-01-01

    This is a Power Point presentation. The following objectives are addressed: A. Determine the target of MOV program; B. Define the strategy for MOV; C. Establish the MOV program execution phases; D. Identification of key parameters; E. Examples. The target of MOV program is to improve the safety by ensuring the adequacy of safety valves and the reliability of safety equipment and, subsequently, to ensure the economic operation of the plant. Consequences of MV malfunction are indicated. The strategy for MOV program development is both general, namely, to define the minimal requirements of preventive /corrective maintenance activities for all MOV's according to design/ manufacture specification and particular, namely to identify MV's specific problems and the need for increasing/decreasing the preventing maintenance tasks or frequency established in 'general' MOV program. Strategy for MOV program development implies: - Establish MOV program applicability; - Develop diagnostic strategy (define key parameters ); - Perform program for engineering review; - Establish program for preventive maintenance; - Revise procedures for operating and maintenance tests; - Dynamic evaluation of MOV. The program execution phases are listed as follows: 1. Perform risk assessment of the MOV's to determine criticality level (program applicability); 2. Collect data to fill in MOV Application Data Sheet; 3. Perform engineering review to determine functional parameters acceptable range and determine key parameters; 4. Analysis for maintenance tasks / frequencies selection and determination of implementing actions (engineer review); 5. Prepare work packages for availability confirmation; 6. Schedule and plan corrective actions or provide input to other programs; 7. Schedule and plan implementing actions in preparation for program field execution; 8. Program field implementation; 9. Program monitoring, evaluation and optimization. The criteria defining the key operational and maintenance

  19. Regulatory standpoints on the design-basis capability of safety-related motor-operated valves(MOVs) and power-operated gate valves(POGVs)

    International Nuclear Information System (INIS)

    Kim, W. T.; Kum, O. H.

    1999-01-01

    The weakness in the design-basis capability of Motor-Operated Valves(MOVs) and the susceptibility to Pressure Locking and Thermal Binding phenomena of Power-Operated Gate Valves(POGVs) have been major concerns to be resolved in the nuclear society in and abroad since Three Mile Island accident occurred in the USA in 1979. Through detailed analysis of operating experience and regulatory activities, some MOVs and POGVs have been found to be unreliable in performing their safety functions when they are required to do so under certain conditions, especially under design-basis accident conditions. Further, it is well understood that these safety problems may not be identified by the typical valve in-service testing(IST). USNRC has published three Generic Letters, GL 89-10, GL 95-07, and GL 96-05, requiring nuclear plant licensees to take appropriate actions to resolve the problems mentioned above. Korean nuclear regulatory body has made public an administration measure called 'Regulatory recommendation to verify safety functions of the safety-related MOVs and POGVs' on June 13, 1997, and in this administration measure Korean utility is asked to submit written documents to show how it assure design-basis capability of these valves. The following are among the major concerns being considered from a regulation standpoint. Program scope and implementation priority, dynamic tests under differential pressure conditions, accuracy of diagnostic equipment, torque switch setting and torque bypass percentage, weak link analysis, motor actuator sizing, corrective actions taken to resolve pressure locking and thermal binding susceptibility, and a periodic verification program for the valves once design-basis capability has been verified

  20. In-service inspection and periodic testing

    International Nuclear Information System (INIS)

    Eisele, H.; Meyer, F.A.; Zipser, R.R.

    1981-01-01

    In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. Below, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor/PWR/ or on a boiling-water reactor/BWR/) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)

  1. In-service inspection and periodic testing

    International Nuclear Information System (INIS)

    Eisele, H.; Meyer, F.A.; Zipser, R.R.

    1980-01-01

    In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. In the present paper, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor/PWR/ or on a boiling-water reactor/BWR/) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)

  2. Enhance pump reliability through improved inservice testing

    International Nuclear Information System (INIS)

    Healy, J.J.

    1990-01-01

    EPRI has undertaken a study to assess the effectiveness of existing testing programs to accurately monitor and predict performance changes before either pump performance degrades or an actual failure occurs. Anticipated changes in inservice testing techniques are directed towards enhancing the validity of test data, ensuring its repeatability, and avoiding deterioration of the pump assembly. There is a new-found interest in test programs of all types that has occurred, in part, because of an increase in reported pump degradation and pump failure. Inservice testing of pumps, which has long been a basis for assuring operability, has apparently produced an opposite effect; namely, the appearance of a reduction in reliability

  3. Guidelines for inservice testing at nuclear power plants

    International Nuclear Information System (INIS)

    Campbell, P.

    1995-04-01

    The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code

  4. Proceedings of the symposium on inservice testing of pumps and valves

    International Nuclear Information System (INIS)

    1990-10-01

    The 1990 Symposium on Inservice Testing of Pumps and Valves, jointly sponsored by the Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provided a forum for the discussion of current programs and methods for inservice testing at nuclear power plants. The symposium also provided an opportunity to discuss the need to improve inservice testing in order to ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants resulted in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants

  5. Proceedings of the symposium on inservice testing of pumps and valves

    Energy Technology Data Exchange (ETDEWEB)

    1990-10-01

    The 1990 Symposium on Inservice Testing of Pumps and Valves, jointly sponsored by the Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provided a forum for the discussion of current programs and methods for inservice testing at nuclear power plants. The symposium also provided an opportunity to discuss the need to improve inservice testing in order to ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants resulted in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants.

  6. Code cases for implementing risk-based inservice testing in the ASME OM code

    International Nuclear Information System (INIS)

    Rowley, C.W.

    1996-01-01

    Historically inservice testing has been reasonably effective, but quite costly. Recent applications of plant PRAs to the scope of the IST program have demonstrated that of the 30 pumps and 500 valves in the typical plant IST program, less than half of the pumps and ten percent of the valves are risk significant. The way the ASME plans to tackle this overly-conservative scope for IST components is to use the PRA and plant expert panels to create a two tier IST component categorization scheme. The PRA provides the quantitative risk information and the plant expert panel blends the quantitative and deterministic information to place the IST component into one of two categories: More Safety Significant Component (MSSC) or Less Safety Significant Component (LSSC). With all the pumps and valves in the IST program placed in MSSC or LSSC categories, two different testing strategies will be applied. The testing strategies will be unique for the type of component, such as centrifugal pump, positive displacement pump, MOV, AOV, SOV, SRV, PORV, HOV, CV, and MV. A series of OM Code Cases are being developed to capture this process for a plant to use. One Code Case will be for Component Importance Ranking. The remaining Code Cases will develop the MSSC and LSSC testing strategy for type of component. These Code Cases are planned for publication in early 1997. Later, after some industry application of the Code Cases, the alternative Code Case requirements will gravitate to the ASME OM Code as appendices

  7. Code cases for implementing risk-based inservice testing in the ASME OM code

    Energy Technology Data Exchange (ETDEWEB)

    Rowley, C.W.

    1996-12-01

    Historically inservice testing has been reasonably effective, but quite costly. Recent applications of plant PRAs to the scope of the IST program have demonstrated that of the 30 pumps and 500 valves in the typical plant IST program, less than half of the pumps and ten percent of the valves are risk significant. The way the ASME plans to tackle this overly-conservative scope for IST components is to use the PRA and plant expert panels to create a two tier IST component categorization scheme. The PRA provides the quantitative risk information and the plant expert panel blends the quantitative and deterministic information to place the IST component into one of two categories: More Safety Significant Component (MSSC) or Less Safety Significant Component (LSSC). With all the pumps and valves in the IST program placed in MSSC or LSSC categories, two different testing strategies will be applied. The testing strategies will be unique for the type of component, such as centrifugal pump, positive displacement pump, MOV, AOV, SOV, SRV, PORV, HOV, CV, and MV. A series of OM Code Cases are being developed to capture this process for a plant to use. One Code Case will be for Component Importance Ranking. The remaining Code Cases will develop the MSSC and LSSC testing strategy for type of component. These Code Cases are planned for publication in early 1997. Later, after some industry application of the Code Cases, the alternative Code Case requirements will gravitate to the ASME OM Code as appendices.

  8. MOV predictive maintenance program at Darlington NGS

    International Nuclear Information System (INIS)

    Morrison, J.F.

    1992-01-01

    This paper details the Motor Operated Valve (MOV) Predictive Maintenance program at Darlington Nuclear Generating Station. The program encompasses the use of diagnostics tooling in conjunction with more standard maintenance techniques, with the goal of improving performance of MOV's. Problems encountered and solutions developed during the first two phases of this program are presented, along with proposed actions for the final trending phase of the program. This paper also touches on the preventive and corrective maintenance aspects of an overall MOV maintenance program. 6 refs., 6 tabs., 6 figs

  9. Allowable stem nut wear and diagnostic monitoring for MOVs

    International Nuclear Information System (INIS)

    Swinburne, P.

    1994-01-01

    After a motor-operated valve (MOV) stem nut failure in 1991 that contributed to a forced plant shutdown, the FitzPatrick Plant staff developed criteria to check for excessive stem nut wear in MOVs. Allowable stem nut wear monitoring uses both direct dimensional measurement and diagnostic test data interpretation. The wear allowance is based on the recommended permitted backlash discussed in the Electric Power Research Institute/Nuclear Maintenance Assistance Center Technical Repair Guideline for the Limitorque SMB-000 Motor Actuator. The diagnostic analysis technique measures the time at zero load and compares this with a precalculated allowable zero force time. Excessive zero force time may be the result of other MOV problems, such as a loose stem nut lock nut or excessive free play in the drive sleeve bearing. Stress levels for new or nominal stem nuts and stem nuts with the full wear allowance were compared. Bending and shear stresses at the thread root increase for the maximum wear condition when compared with a open-quotes newclose quotes stem nut. These stresses are directly related to the thread root thickness. For typical MOV loading and common stem threading (with two diameters of thread engagement), the thread stresses are well within acceptable limits for ASTM B584-C86300 (formerly B147-863) manganese bronze (typical stem nut material)

  10. The effects of aging on friction of MOVs

    International Nuclear Information System (INIS)

    Hunt, T.H.; Sinha, U.P.

    1991-01-01

    This report studied the effect of three aging mechanisms: corrosion, erosion, and deposition on the friction coefficients of the sliding surfaces of motor-operated valves (MOVs) used in nuclear plant systems. The US Nuclear Regulatory Commission (NRC) sponsored the study, and it was performed following the guidelines of their Nuclear Plant Aging Research (NPAR) program. The authors reached three general conclusions: corrosion and deposition should not prevent valve operation by obstructing the mechanical tolerances of the MOVs; the aging mechanisms may increase the friction coefficients due to roughening the surfaces with age; and the codes and standards defining MOV surveillance requirements need review to include methods for detecting aging degradation

  11. Guidelines for inservice testing at nuclear power plants. Draft report for comment

    International Nuclear Information System (INIS)

    Campbell, P.

    1993-11-01

    In this report, the staff gives licensees guidelines for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The report includes U.S. Nuclear Regulatory Commission (NRC) guidance and recommendations on inservice testing issues. The staff discusses the regulations, the components to be included in an inservice testing program, and the preparation and content of cold shutdown and refueling outage justifications and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information for application at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code

  12. A VITAL service for predictive MOV maintenance

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    Motor-operated valve (MOV) maintenance can be a major contributor to unplanned plant downtime, either because valve malfunctions cause unscheduled outages, or because unnecessary valve maintenance lengthens scheduled outages. The cause of both situations is a preventive approach to valve maintenance, where maintenance is scheduled according to a timetable instead of according to a demonstrated need. To move towards a predictive maintenance approach, inexpensive methods of collecting and diagnosing real-time data on the conditions of a valve must be made available. Such a system must be capable of detecting and diagnosing degrading mechanical and electrical behaviour at an early stage, as well as being able to predict the time of failure. Without this data, a predictive approach to maintenance is impossible. Westinghouse is addressing the requirements for a predictive approach to MOV maintenance with the introduction of a third-generation of diagnostic systems for motor-operated valves -the portable Valve Intelligent Test and Analysis System (VITALS) and the on-line Valve Monitoring System (VMS). (author)

  13. Adaptive settings of distance relay for MOV-protected series compensated line with distributed capacitance considering wind power

    Science.gov (United States)

    Sivov, Oleg Viktorovich

    Series compensated lines are protected from overvoltage by metal-oxide-varistors (MOVs) connected in parallel with the capacitor bank. The nonlinear characteristics of MOV devices add complexity to fault analysis and distance protection operation. During faults, the impedance of the line is modified by an equivalent impedance of the parallel MOV/capacitor circuit, which affects the distance protection. The intermittent wind generation introduces additional complexity to the system performance and distance protection. Wind variation affects the fault current level and equivalent MOV/capacitor impedance during a fault, and hence the distance relay operation. This thesis studies the impact of the intermittent wind power generation on the operation of MOV during faults. For the purpose of simulation, an equivalent wind farm model is proposed to generate a wind generation profile using wind farm generation from California independent system operator (ISO) as a guide for wind power variation to perform the study. The IEEE 12-bus test system is modified to include MOV-protected series capacitor and the equivalent wind farm model. The modified test system is simulated in the MATLAB/Simulink environment. The study has been achieved considering three phase and single line to ground (SLG) faults on the series compensated line to show the effect of wind variation on the MOV operation. This thesis proposes an adaptive setting method for the mho relay distance protection of series compensated line considering effects of wind power variation and MOV operation. The distributed parameters of a transmission line are taken into account to avoid overreaching and underreaching of distance relays. The study shows that variable wind power affects system power flow and fault current in the compensated line during a fault which affects the operation of MOVs for different fault conditions. The equivalent per-phase impedance of the MOV/capacitor circuit has an effect on the system operation

  14. Risk informed in-service inspection and testing in Spain

    International Nuclear Information System (INIS)

    Bros, Juan; Marcelles, Ignacio

    2002-01-01

    The Spanish nuclear regulatory authority, the Consejo de Seguridad Nuclear (CSN), requires the use of codes and standards in force in the country of origin of the plant technology. For this reason, the in-service inspection and testing programs applied at Spanish nuclear power plants basically adhere to the requirements of the ASME XI and ASME OM Codes. It is not surprising that when the earliest developments aimed at drawing up risk informed inservice inspection and testing programs were initiated within the framework of ASME, the Spanish industry should follows such developments very closely. In fact, persons within the Spanish nuclear industry joined different ASME committees involved in the development and approval of the various code cases encompassing these developments. Developments specific to the Spanish nuclear power plants were initiated at a time when the aforementioned reference documentation was in a very advanced stage of development/approval. Two clearly differentiated lines of work got under way: On the one hand, and as regards risk informed in-service testing programs, the American standards were used as the sole reference. In the case of risk informed in-service inspection programs, the Spanish nuclear power plant-owning utilities and the Consejo de Seguridad Nuclear decided to draw up a Spanish guideline that, although using the ASME developments as a reference, would have its own specific characteristics. In relation to the above, and referring to the chronology of the events, the activities performed to date in Spain are described

  15. MOV10 RNA helicase is a potent inhibitor of retrotransposition in cells.

    Directory of Open Access Journals (Sweden)

    John L Goodier

    Full Text Available MOV10 protein, a putative RNA helicase and component of the RNA-induced silencing complex (RISC, inhibits retrovirus replication. We show that MOV10 also severely restricts human LINE1 (L1, Alu, and SVA retrotransposons. MOV10 associates with the L1 ribonucleoprotein particle, along with other RNA helicases including DDX5, DHX9, DDX17, DDX21, and DDX39A. However, unlike MOV10, these other helicases do not strongly inhibit retrotransposition, an activity dependent upon intact helicase domains. MOV10 association with retrotransposons is further supported by its colocalization with L1 ORF1 protein in stress granules, by cytoplasmic structures associated with RNA silencing, and by the ability of MOV10 to reduce endogenous and ectopic L1 expression. The majority of the human genome is repetitive DNA, most of which is the detritus of millions of years of accumulated retrotransposition. Retrotransposons remain active mutagens, and their insertion can disrupt gene function. Therefore, the host has evolved defense mechanisms to protect against retrotransposition, an arsenal we are only beginning to understand. With homologs in other vertebrates, insects, and plants, MOV10 may represent an ancient and innate form of immunity against both infective viruses and endogenous retroelements.

  16. Analysis of thrust/torque signature of MOV

    International Nuclear Information System (INIS)

    Ryu, Ho Geun; Park, Seong Keun; Kim, Dae Woong

    2001-01-01

    For the evaluation of operability of MOV(Motor Operated Valve), the precision prediction of thrust/torque acting on the valve is important. In this paper, the analytical prediction method of thrust/torque was proposed. The design basis stem thrust calculation typically considers the followings: packing thrust, stem rejection load, design basis differential pressure load. In general, test results show that temperature, pressure, fluid type, and differential pressure, independently and combination, all have an effect on the friction factor. The prediction results of thrust/torque are well agreement with dynamic test results

  17. Experience and benefits from using the EPRI MOV Performance Prediction Methodology in nuclear power plants

    International Nuclear Information System (INIS)

    Walker, T.; Damerell, P.S.

    1999-01-01

    The EPRI MOV Performance Prediction Methodology (PPM) is an effective tool for evaluating design basis thrust and torque requirements for MOVs. Use of the PPM has become more widespread in US nuclear power plants as they close out their Generic Letter (GL) 89-10 programs and address MOV periodic verification per GL 96-05. The PPM has also been used at plants outside the US, many of which are implementing programs similar to US plants' GL 89-10 programs. The USNRC Safety Evaluation of the PPM and the USNRC's discussion of the PPM in GL 96-05 make the PPM an attractive alternative to differential pressure (DP) testing, which can be costly and time-consuming. Significant experience and benefits, which are summarized in this paper, have been gained using the PPM. Although use of PPM requires a commitment of resources, the benefits of a solidly justified approach and a reduced need for DP testing provide a substantial safety and economic benefit. (author)

  18. Experimental and clinical analysis of the characteristics of a chimeric monoclonal antibody, MOv18, reactive with an ovarian cancer-associated antigen

    NARCIS (Netherlands)

    Molthoff, C. F.; Buist, M. R.; Kenemans, P.; Pinedo, H. M.; Boven, E.

    1992-01-01

    Monoclonal antibody (Mab) MOv18 preferentially reacts with gynecological carcinomas. We have analyzed the characteristics of murine MOv18 (m-MOv18) and chimeric MOv18 (c-MOv18). We found no differences in affinity and binding to IGROV1 cells between c-MOv18 as IgG and F(ab')2 fragments and m-MOv18.

  19. Endogenous MOV10 inhibits the retrotransposition of endogenous retroelements but not the replication of exogenous retroviruses.

    Science.gov (United States)

    Arjan-Odedra, Shetal; Swanson, Chad M; Sherer, Nathan M; Wolinsky, Steven M; Malim, Michael H

    2012-06-22

    The identification of cellular factors that regulate the replication of exogenous viruses and endogenous mobile elements provides fundamental understanding of host-pathogen relationships. MOV10 is a superfamily 1 putative RNA helicase that controls the replication of several RNA viruses and whose homologs are necessary for the repression of endogenous mobile elements. Here, we employ both ectopic expression and gene knockdown approaches to analyse the role of human MOV10 in the replication of a panel of exogenous retroviruses and endogenous retroelements. MOV10 overexpression substantially decreased the production of infectious retrovirus particles, as well the propagation of LTR and non-LTR endogenous retroelements. Most significantly, RNAi-mediated silencing of endogenous MOV10 enhanced the replication of both LTR and non-LTR endogenous retroelements, but not the production of infectious retrovirus particles demonstrating that natural levels of MOV10 suppress retrotransposition, but have no impact on infection by exogenous retroviruses. Furthermore, functional studies showed that MOV10 is not necessary for miRNA or siRNA-mediated mRNA silencing. We have identified novel specificity for human MOV10 in the control of retroelement replication and hypothesise that MOV10 may be a component of a cellular pathway or process that selectively regulates the replication of endogenous retroelements in somatic cells.

  20. Endogenous MOV10 inhibits the retrotransposition of endogenous retroelements but not the replication of exogenous retroviruses

    Science.gov (United States)

    2012-01-01

    Background The identification of cellular factors that regulate the replication of exogenous viruses and endogenous mobile elements provides fundamental understanding of host-pathogen relationships. MOV10 is a superfamily 1 putative RNA helicase that controls the replication of several RNA viruses and whose homologs are necessary for the repression of endogenous mobile elements. Here, we employ both ectopic expression and gene knockdown approaches to analyse the role of human MOV10 in the replication of a panel of exogenous retroviruses and endogenous retroelements. Results MOV10 overexpression substantially decreased the production of infectious retrovirus particles, as well the propagation of LTR and non-LTR endogenous retroelements. Most significantly, RNAi-mediated silencing of endogenous MOV10 enhanced the replication of both LTR and non-LTR endogenous retroelements, but not the production of infectious retrovirus particles demonstrating that natural levels of MOV10 suppress retrotransposition, but have no impact on infection by exogenous retroviruses. Furthermore, functional studies showed that MOV10 is not necessary for miRNA or siRNA-mediated mRNA silencing. Conclusions We have identified novel specificity for human MOV10 in the control of retroelement replication and hypothesise that MOV10 may be a component of a cellular pathway or process that selectively regulates the replication of endogenous retroelements in somatic cells. PMID:22727223

  1. {sup 177}Lu- labeled MOv18 as compared to {sup 131}I- or {sup 90}Y-labeled MOv18 has the better therapeutic effect in eradication of alpha folate receptor-expressing tumor xenografts

    Energy Technology Data Exchange (ETDEWEB)

    Zacchetti, Alberto [Unit of Molecular Therapies, Department of Experimental Oncology and Laboratories, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy); Coliva, Angela [Department of Imaging and Nuclear Medicine, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy); Luison, Elena [Unit of Molecular Therapies, Department of Experimental Oncology and Laboratories, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy); Seregni, Ettore; Bombardieri, Emilio [Department of Imaging and Nuclear Medicine, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy); Giussani, Augusto [Helmholtz Zentrum Muenchen, German Research Center for Environmental Health, Neuherberg (Germany); Figini, Mariangela [Unit of Molecular Therapies, Department of Experimental Oncology and Laboratories, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy); Canevari, Silvana [Unit of Molecular Therapies, Department of Experimental Oncology and Laboratories, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy)], E-mail: silvana.canevari@istitutotumori.mi.it

    2009-10-15

    Introduction: The mouse monoclonal antibody MOv18, directed against the {alpha}-isoform of folate receptor (FR), was investigated to identify the optimal radioconjugate for radioimmunotherapy of minimal residual disease in ovarian cancer. Methods: Pharmacokinetics, biodistribution, long-term therapeutic efficacy and toxicity of MOv18, labeled with the beta-emitters {sup 131}I, {sup 90}Y and {sup 177}Lu, were compared in a xenografted mouse model, composed by two cell lines, A431FR and A431MK, differing only for FR expression. Results: A shorter blood clearance and a higher tumor uptake were observed for {sup 90}Y- and {sup 177}Lu- compared to {sup 131}I-MOv18, and a shorter blood pharmacokinetics was recorded in A431FR-bearing animals. At equitoxic maximum tolerable doses, the general irradiation by {sup 131}I- and {sup 90}Y-MOv18 gives rise to strong targeted effects on A431FR and nontargeted effects on A431MK tumors, while {sup 177}Lu-MOv18 was able to eradicate small size tumor masses expressing the antigen of interest exerting only mild non-targeted effects. Conclusion: {sup 177}Lu-MOv18 at the maximal tolerated dose is the immunoradioconjugate with the best therapeutic window in experimental conditions of small tumor volume.

  2. The application of RCM to ASME code requirements for in-service testing

    International Nuclear Information System (INIS)

    Rowley, C.W.

    1990-01-01

    This paper reports that the high reliability of nuclear power plant systems and components is highly important for both nuclear safety and electrical power production economics. The optimum operating performance of these plant systems and components is heavily dependent on the original or modified design for its inherent reliability and the appropriate trade-off in preventive and corrective maintenance for its developed reliability. In developing this optimum operating performance goal, the plant staff could rely solely on the experience of its personnel. However using this internal subjective approach, the average nuclear power availability has been far less than 80%. Obviously the production economics of a nuclear power plant is the province of the owner-operator, but the safety system and component performance impacts the entire industry. Hence the nuclear industry needs to have in-service testing requirements that maintain the necessary safety standards. Historically the ASME Inservice Testing Code has been a vehicle for defining some of those necessary safety standards, such as inservice testing of pumps, valves, and snubbers. The nuclear industry needs to expand the code testing to include all the systems that affect these necessary safety standards

  3. Applying reliability centered maintenance analysis principles to inservice testing

    International Nuclear Information System (INIS)

    Flude, J.W.

    1994-01-01

    Federal regulations require nuclear power plants to use inservice test (IST) programs to ensure the operability of safety-related equipment. IST programs are based on American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code requirements. Many of these plants also use Reliability Centered Maintenance (RCM) to optimize system maintenance. ASME Code requirements are hard to change. The process for requesting authority to use an alternate strategy is long and expensive. The difficulties of obtaining this authority make the use of RCM method on safety-related systems not cost effective. An ASME research task force on Risk Based Inservice Testing is investigating changing the Code. The change will allow plants to apply RCM methods to the problem of maintenance strategy selection for safety-related systems. The research task force is working closely with the Codes and Standards sections to develop a process related to the RCM process. Some day plants will be able to use this process to develop more efficient and safer maintenance strategies

  4. Inservice testing of vertical pumps

    International Nuclear Information System (INIS)

    Cornman, R.E. Jr.; Schumann, K.E.

    1994-01-01

    This paper focuses on the problems that may occur with vertical pumps while inservice tests are conducted in accordance with existing American Society of Mechanical Engineers Code, Section XI, standards. The vertical pump types discussed include single stage, multistage, free surface, and canned mixed flow pumps. Primary emphasis is placed on the hydraulic performance of the pump and the internal and external factors to the pump that impact hydraulic performance. In addition, the paper considers the mechanical design features that can affect the mechanical performance of vertical pumps. The conclusion shows how two recommended changes in the Code standards may increase the quality of the pump's operational readiness assessment during its service life

  5. The current state of inservice testing programs at U.S. Nuclear Power Plants - a regulatory overview

    International Nuclear Information System (INIS)

    Campbell, P.; Colaccino, J.

    1994-01-01

    Information is provided on inservice testing (IST) of pumps and valves at U.S. nuclear power plants to provide consistency in the implementation of regulatory requirements and to enhance communications among utility licensees who may have, like NSSS vendors, similar kinds and numbers of components or comparable IST programs. Documents discussed include the ASME Operation and Maintenance Standards Parts 6 and 10 (covering inservice testing of pumps and valves in light water reactor power plants), the draft NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants (including review comments by Nuclear Management and Resource Council), and applicable Licensee Event Reports including summaries of several reports relating to IST

  6. Predictable or not predictable? The MOV question

    International Nuclear Information System (INIS)

    Thibault, C.L.; Matzkiw, J.N.; Anderson, J.W.; Kessler, D.W.

    1994-01-01

    Over the past 8 years, the nuclear industry has struggled to understand the dynamic phenomena experienced during motor-operated valve (MOV) operation under differing flow conditions. For some valves and designs, their operational functionality has been found to be predictable; for others, unpredictable. Although much has been accomplished over this period of time, especially on modeling valve dynamics, the unpredictability of many valves and designs still exists. A few valve manufacturers are focusing on improving design and fabrication techniques to enhance product reliability and predictability. However, this approach does not address these issues for installed and inpredictable valves. This paper presents some of the more promising techniques that Wyle Laboratories has explored with potential for transforming unpredictable valves to predictable valves and for retrofitting installed MOVs. These techniques include optimized valve tolerancing, surrogated material evaluation, and enhanced surface treatments

  7. Use of expert judgment in the development and evaluation of risk-based inservice testing strategies for pumps and valves

    International Nuclear Information System (INIS)

    McAllister, W.J.; Perdue, R.K.; Balkey, K.R.; Closky, N.B.

    1996-01-01

    This paper describes a rigorous approach for quantitatively evaluating inservice testing effectiveness that evolved from two pilot plant studies. These studies prototyped methodologies for designing and selecting inservice testing (IST) strategies in a manner structured to insure that the targeted components will perform their required safety functions while minimizing life cycle inservice testing costs. The paper concentrates on the use of expert judgment in developing test effectiveness measures that move risk-based methods beyond ranking to optimization of plant IST programs. Selected results for check valves and pumps are shown to illustrate the practical significance of the approach

  8. Use of expert judgment in the development and evaluation of risk-based inservice testing strategies for pumps and valves

    Energy Technology Data Exchange (ETDEWEB)

    McAllister, W.J.; Perdue, R.K.; Balkey, K.R.; Closky, N.B. [and others

    1996-12-01

    This paper describes a rigorous approach for quantitatively evaluating inservice testing effectiveness that evolved from two pilot plant studies. These studies prototyped methodologies for designing and selecting inservice testing (IST) strategies in a manner structured to insure that the targeted components will perform their required safety functions while minimizing life cycle inservice testing costs. The paper concentrates on the use of expert judgment in developing test effectiveness measures that move risk-based methods beyond ranking to optimization of plant IST programs. Selected results for check valves and pumps are shown to illustrate the practical significance of the approach.

  9. Review of Savannah River Site K Reactor inservice inspection and testing restart program

    International Nuclear Information System (INIS)

    Anderson, M.T.; Hartley, R.S.; Kido, C.

    1992-09-01

    Inservice inspection (ISI) and inservice testing (IST) programs are used at commercial nuclear power plants to monitor the pressure boundary integrity and operability of components in important safety-related systems. The Department of Energy (DOE) - Office of Defense Programs (DP) operates a Category A (> 20 MW thermal) production reactor at the Savannah River Site (SRS). This report represents an evaluation of the ISI and IST practices proposed for restart of SRS K Reactor as compared, where applicable, to current ISI/IST activities of commercial nuclear power facilities

  10. RNA helicase MOV10 functions as a co-factor of HIV-1 Rev to facilitate Rev/RRE-dependent nuclear export of viral mRNAs

    International Nuclear Information System (INIS)

    Huang, Feng; Zhang, Junsong; Zhang, Yijun; Geng, Guannan; Liang, Juanran; Li, Yingniang; Chen, Jingliang; Liu, Chao; Zhang, Hui

    2015-01-01

    Human immunodeficiency virus type 1 (HIV-1) exploits multiple host factors during its replication. The REV/RRE-dependent nuclear export of unspliced/partially spliced viral transcripts needs the assistance of host proteins. Recent studies have shown that MOV10 overexpression inhibited HIV-1 replication at various steps. However, the endogenous MOV10 was required in certain step(s) of HIV-1 replication. In this report, we found that MOV10 potently enhances the nuclear export of viral mRNAs and subsequently increases the expression of Gag protein and other late products through affecting the Rev/RRE axis. The co-immunoprecipitation analysis indicated that MOV10 interacts with Rev in an RNA-independent manner. The DEAG-box of MOV10 was required for the enhancement of Rev/RRE-dependent nuclear export and the DEAG-box mutant showed a dominant-negative activity. Our data propose that HIV-1 utilizes the anti-viral factor MOV10 to function as a co-factor of Rev and demonstrate the complicated effects of MOV10 on HIV-1 life cycle. - Highlights: • MOV10 can function as a co-factor of HIV-1 Rev. • MOV10 facilitates Rev/RRE-dependent transport of viral mRNAs. • MOV10 interacts with Rev in an RNA-independent manner. • The DEAG-box of MOV10 is required for the enhancement of Rev/RRE-dependent export.

  11. RNA helicase MOV10 functions as a co-factor of HIV-1 Rev to facilitate Rev/RRE-dependent nuclear export of viral mRNAs

    Energy Technology Data Exchange (ETDEWEB)

    Huang, Feng; Zhang, Junsong; Zhang, Yijun; Geng, Guannan; Liang, Juanran; Li, Yingniang; Chen, Jingliang [Institute of Human Virology, Zhongshan School of Medicine, Sun Yat-sen University, Guangzhou 510080 (China); Key Laboratory of Tropical Disease Control of Ministry of Education, Zhongshan School of Medicine, Sun Yat-sen University, Guangzhou 510080 (China); Liu, Chao, E-mail: liuchao9@mail.sysu.edu.cn [Institute of Human Virology, Zhongshan School of Medicine, Sun Yat-sen University, Guangzhou 510080 (China); Key Laboratory of Tropical Disease Control of Ministry of Education, Zhongshan School of Medicine, Sun Yat-sen University, Guangzhou 510080 (China); Zhang, Hui [Institute of Human Virology, Zhongshan School of Medicine, Sun Yat-sen University, Guangzhou 510080 (China); Key Laboratory of Tropical Disease Control of Ministry of Education, Zhongshan School of Medicine, Sun Yat-sen University, Guangzhou 510080 (China)

    2015-12-15

    Human immunodeficiency virus type 1 (HIV-1) exploits multiple host factors during its replication. The REV/RRE-dependent nuclear export of unspliced/partially spliced viral transcripts needs the assistance of host proteins. Recent studies have shown that MOV10 overexpression inhibited HIV-1 replication at various steps. However, the endogenous MOV10 was required in certain step(s) of HIV-1 replication. In this report, we found that MOV10 potently enhances the nuclear export of viral mRNAs and subsequently increases the expression of Gag protein and other late products through affecting the Rev/RRE axis. The co-immunoprecipitation analysis indicated that MOV10 interacts with Rev in an RNA-independent manner. The DEAG-box of MOV10 was required for the enhancement of Rev/RRE-dependent nuclear export and the DEAG-box mutant showed a dominant-negative activity. Our data propose that HIV-1 utilizes the anti-viral factor MOV10 to function as a co-factor of Rev and demonstrate the complicated effects of MOV10 on HIV-1 life cycle. - Highlights: • MOV10 can function as a co-factor of HIV-1 Rev. • MOV10 facilitates Rev/RRE-dependent transport of viral mRNAs. • MOV10 interacts with Rev in an RNA-independent manner. • The DEAG-box of MOV10 is required for the enhancement of Rev/RRE-dependent export.

  12. Reproducibility problems of in-service ultrasonic testing results

    International Nuclear Information System (INIS)

    Honcu, E.

    1974-01-01

    The reproducibility of the results of ultrasonic testing is the basic precondition for its successful application in in-service inspection of changes in the quality of components of nuclear power installations. The results of periodic ultrasonic inspections are not satisfactory from the point of view of reproducibility. Regardless, the ultrasonic pulse-type method is suitable for evaluating the quality of most components of nuclear installations and often the sole method which may be recommended for inspection with regard to its technical and economic aspects. (J.B.)

  13. Summary of inspection findings of licensee inservice testing programs at United States commercial nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Dunlop, A.; Colaccino, J.

    1996-12-01

    Periodic inspections of pump and valve inservice testing (IST) programs in United States commercial nuclear power plants are performed by Nuclear Regulatory Commission (NRC) Regional Inspectors to verify licensee regulatory compliance and licensee commitments. IST inspections are conducted using NRC Inspection Procedure 73756, {open_quotes}Inservice Testing of Pumps and Valves{close_quotes} (IP 73756), which was updated on July 27, 1995. A large number of IST inspections have also been conducted using Temporary Instruction 2515/114, {open_quotes}Inspection Requirements for Generic Letter 89-04, Acceptable Inservice Testing Programs{close_quotes} (TI-2515/114), which was issued January 15, 1992. A majority of U.S. commercial nuclear power plants have had an IST inspection to either IP 73756 or TI 2515/114. This paper is intended to summarize the significant and recurring findings from a number of these inspections since January of 1990.

  14. Safety significance of component ageing, exemplary for MOV, based on French and German operating experience

    Energy Technology Data Exchange (ETDEWEB)

    Morlent, O. [CEA Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Michel, F. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Garching (Germany)

    2001-07-01

    An outline is given of how IPSN and GRS assess the effects of physical ageing on the safety of French and German Nuclear Power Plants (NPPs) on the basis of the available knowledge and how investigations are carried out. The presentation is focused exemplary on a preliminary study illustrating approaches for the evaluation of the ageing behaviour of active components, the motor-operated valves (MOV). The results so far seems to demonstrate that the developed methodological approaches are suitable to obtain qualitative evidence with regard to the ageing behaviour of technical facilities such as MOV. The evaluation of the operating experience with French 900 MWe plants seems to reveal, for MOV of one system, a trend similar to some international findings about ageing-related events with increasing operating time; this trend will have to be confirmed. For the German NPPs so far, there appears to be no significant increase of ageing-related events concerning MOV as the plants get older. Future work on ageing scheduled at IPSN and GRS includes further cooperation on this issue, too; a deep analysis is necessary to explain the reasons of such apparent differences before any conclusion. (authors)

  15. Safety significance of component ageing, exemplary for MOV, based on French and German operating experience

    International Nuclear Information System (INIS)

    Morlent, O.

    2001-01-01

    An outline is given of how IPSN and GRS assess the effects of physical ageing on the safety of French and German Nuclear Power Plants (NPPs) on the basis of the available knowledge and how investigations are carried out. The presentation is focused exemplary on a preliminary study illustrating approaches for the evaluation of the ageing behaviour of active components, the motor-operated valves (MOV). The results so far seems to demonstrate that the developed methodological approaches are suitable to obtain qualitative evidence with regard to the ageing behaviour of technical facilities such as MOV. The evaluation of the operating experience with French 900 MWe plants seems to reveal, for MOV of one system, a trend similar to some international findings about ageing-related events with increasing operating time; this trend will have to be confirmed. For the German NPPs so far, there appears to be no significant increase of ageing-related events concerning MOV as the plants get older. Future work on ageing scheduled at IPSN and GRS includes further cooperation on this issue, too; a deep analysis is necessary to explain the reasons of such apparent differences before any conclusion. (authors)

  16. The orientation dependence of the hydrogen distribution within Mo/V (110) and (001) multilayered artificial superlattices

    CERN Document Server

    Hjörvarsson, B; Olafsson, S; Karlsson, E B; Birch, J; Sundgren, J E

    1997-01-01

    We have investigated the hydrogen distribution within multilayered Mo/V (110) and (001) artificial superlattices. The hydrogen concentration, determined by the sup 1 H( sup 1 sup 5 N, alpha gamma) sup 1 sup 2 C nuclear resonance reaction, is found to decrease with decreasing layer thickness. The decrease is attributed to an interface region with reduced hydrogen content. The extension of this interface region is found to be two monolayers in Mo/V (110), compared to the previously reported three monolayers in Mo/V (001) superlattices. In the (110) oriented samples the relative amount of H in the interface region decreases with increasing average H content (H/V (atomicratio) approx. 0.3-0.5). This effect is shown to be related to the orientation of the hydrogen planes with respect to the boundaries implied by the Mo/V interfaces. The hydrogen induced volume change, obtained by conventional theta-2 theta x-ray diffraction (XRD) and reciprocal space mapping, is found to be smaller for the (110) samples than for t...

  17. A soft computing scheme incorporating ANN and MOV energy in fault detection, classification and distance estimation of EHV transmission line with FSC.

    Science.gov (United States)

    Khadke, Piyush; Patne, Nita; Singh, Arvind; Shinde, Gulab

    2016-01-01

    In this article, a novel and accurate scheme for fault detection, classification and fault distance estimation for a fixed series compensated transmission line is proposed. The proposed scheme is based on artificial neural network (ANN) and metal oxide varistor (MOV) energy, employing Levenberg-Marquardt training algorithm. The novelty of this scheme is the use of MOV energy signals of fixed series capacitors (FSC) as input to train the ANN. Such approach has never been used in any earlier fault analysis algorithms in the last few decades. Proposed scheme uses only single end measurement energy signals of MOV in all the 3 phases over one cycle duration from the occurrence of a fault. Thereafter, these MOV energy signals are fed as input to ANN for fault distance estimation. Feasibility and reliability of the proposed scheme have been evaluated for all ten types of fault in test power system model at different fault inception angles over numerous fault locations. Real transmission system parameters of 3-phase 400 kV Wardha-Aurangabad transmission line (400 km) with 40 % FSC at Power Grid Wardha Substation, India is considered for this research. Extensive simulation experiments show that the proposed scheme provides quite accurate results which demonstrate complete protection scheme with high accuracy, simplicity and robustness.

  18. Diagnosing MOV problems using comparative trace analysis

    International Nuclear Information System (INIS)

    Leon, R.L.

    1992-01-01

    The paper presents the concept of comparative trace analysis and shows it to be very effective in diagnosing motor operated valve (MOV) problems. Comparative trace analysis is simply the process of interpreting simultaneously gathered traces, each presenting a different perspective on the same series of events. The opening and closing of a motor operated valve is such a series of events. The simultaneous traces are obtained using Liberty Technologies' Valve Operation Test and Evaluation System (VOTES)reg-sign. The traces include stem thrust, motor current, motor power factor, motor power, switch actuations, vibration in three different frequency bands, spring pack displacement, and spring pack force. Spare and auxiliary channels enable additional key parameters to be measured, such as differential pressure and stem displacement. Though not specifically illustrated in this paper, the VOTES system also provides for FFT analysis on all traces except switches

  19. In-service inspection techniques

    International Nuclear Information System (INIS)

    Backfisch, W.; Zipser, R.R.

    1980-01-01

    The owner of a nuclear power plant (NPP) is obligated and interested to maintain - by regular maintenance and in-service inspections - the operational safety and availability of the plant for the subsequent operating period in a condition, as is specified as the basis of the erection and the last operational permits. In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. Below, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor or on a boiling-water reactor) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)

  20. Low-Cycle Fatigue Behavior of 10CrNi3MoV High Strength Steel and Its Undermatched Welds.

    Science.gov (United States)

    Song, Wei; Liu, Xuesong; Berto, Filippo; Razavi, S M J

    2018-04-24

    The use of high strength steel allows the design of lighter, more slender and simpler structures due to high strength and favorable ductility. Nevertheless, the increase of yield strength does not guarantee the corresponding improvement of fatigue resistance, which becomes a major concern for engineering structure design, especially for the welded joints. The paper presents a comparison of the low cycle fatigue behaviors between 10CrNi3MoV high strength steel and its undermatched weldments. Uniaxial tension tests, Push-pull, strain-controlled fatigue tests were conducted on base metal and weldments in the strain range of 0.2⁻1.2%. The monotonic and cyclic stress-strain curves, stress-life, strain-life and energy-life in terms of these materials were analyzed for fatigue assessment of materials discrepancy. The stress-life results of base metal and undermatched weld metal exhibit cyclic softening behaviors. Furthermore, the shapes of 10CrNi3MoV steel hysteresis loops show a satisfactory Masing-type behavior, while the weld metal shows a non-Masing type behavior. Strain, plastic and total strain energy density amplitudes against the number of reversals to failure results demonstrate that the undermatched weld metal presents a higher resistance to fatigue crack initiation than 10CrNi3MoV high strength steel. Finally, fatigue fracture surfaces of specimens were compared by scanning electron microscopy to identify the differences of crack initiation and the propagation between them.

  1. Low-Cycle Fatigue Behavior of 10CrNi3MoV High Strength Steel and Its Undermatched Welds

    Directory of Open Access Journals (Sweden)

    Wei Song

    2018-04-01

    Full Text Available The use of high strength steel allows the design of lighter, more slender and simpler structures due to high strength and favorable ductility. Nevertheless, the increase of yield strength does not guarantee the corresponding improvement of fatigue resistance, which becomes a major concern for engineering structure design, especially for the welded joints. The paper presents a comparison of the low cycle fatigue behaviors between 10CrNi3MoV high strength steel and its undermatched weldments. Uniaxial tension tests, Push-pull, strain-controlled fatigue tests were conducted on base metal and weldments in the strain range of 0.2–1.2%. The monotonic and cyclic stress-strain curves, stress-life, strain-life and energy-life in terms of these materials were analyzed for fatigue assessment of materials discrepancy. The stress-life results of base metal and undermatched weld metal exhibit cyclic softening behaviors. Furthermore, the shapes of 10CrNi3MoV steel hysteresis loops show a satisfactory Masing-type behavior, while the weld metal shows a non-Masing type behavior. Strain, plastic and total strain energy density amplitudes against the number of reversals to failure results demonstrate that the undermatched weld metal presents a higher resistance to fatigue crack initiation than 10CrNi3MoV high strength steel. Finally, fatigue fracture surfaces of specimens were compared by scanning electron microscopy to identify the differences of crack initiation and the propagation between them.

  2. In-service materials testing of selected components of unit 1 and 2 of V-1 nuclear power plant

    International Nuclear Information System (INIS)

    Cintula, J.

    1982-01-01

    The task of in-service nondestructive testing of nuclear installations is to confirm that the state of base material and welded joints has not changed owing to mechanical, thermal or radiation stress. Under the regulations of safe operation the first in-service inspection of all components of a WWER 440 reactor must be carried out after 15,000 to 2O,00O operating hours at the latest. Further in-service inspections are repeated after 30,000 hours (pressure vessels) and 40,000 hours (the main steam piping and the feedwater piping). Proceeding from experience gained so far, intervals are suggested for in-service checks of the other components of the V-1 nuclear power plant. Also briefly described are the main nondestructive methods used for such checks at this power plant. (Z.M.)

  3. Launcher In-Service Workspace

    Data.gov (United States)

    Federal Laboratory Consortium — Purpose:Through Engineering Investigations (EIs), testing, development, evaluation and system integration of Aircraft Launch and Recovery Equipment (ALRE) in-service...

  4. 77 FR 12089 - Proposed Generic Communication; Regulatory Issue Summary 2012-XX: Developing Inservice Testing...

    Science.gov (United States)

    2012-02-28

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0048] Proposed Generic Communication; Regulatory Issue... CFR) Part 52, ``Licenses, Certifications, and Approvals for Nuclear Power Plants,'' to satisfy the... inservice testing programs during the initial 120-month program interval following nuclear power plant...

  5. Ten-year rollover of San Onofre inservice testing program for pumps and valves to OM-6 and OM-10

    International Nuclear Information System (INIS)

    Croy, P.A.; Fischetti, S.; Chiang, D.; Schofield, P.; Barney, D.

    1994-01-01

    The Pump and Valve Inservice Testing (IST) Program Sat San Onofre, Units 2 and 3, was updated for the second 120-month interval from August 1993 to April 1994. The U.S. Nuclear Regulatory Commission (USNRC) approved the OM-6 and OM-10 Codes in mid-1992. The project for the rollover to these new Codes included several elements: (a) a review of the differences between IWV/IWP and OM-6/OM-10, (b) a comprehensive audit of the IST Program scope for valves, (c) creation of the program and supporting basis documents, the Relief Requests, and implementing procedures, (d) interdivisional coordination, (e) submittal to the USNRC, and (f) training. Subsections IWV and IWP have been used and essentially unchanged for over a decade. The new Code (Parts 1, 6, and 10 called OM-1, OM-6, and OM-10) includes several significant changes from the old Code. Our group identified these differences and drafted revised and reorganized Inservice Testing (IST) Program documents. We also considered USNRC Generic Letter 89-04 (GL 89-04), open-quotes Guidance on Developing Acceptable Inservice Testing Programsclose quotes, and NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants, while revising the program. There were six pump relief requires and 13 valve relief requests in the program for the first 10-year interval. For the revised program we needed only one pump relief request (and no valve relief requests). Converting to the 1989 edition of the ASME Code did not require changes to the technical specifications. We revised our Updated Final Safety Analysis Report (UFSAR) to reflect the IST Program for the second 10-year interval. UFSAR changes were minor, consisting of updated references to the Code edition and 10 CFR 50.55a(f), open-quotes Inservice Testing Requirementsclose quotes

  6. Facilities for in-service control

    International Nuclear Information System (INIS)

    Werner, H.

    1980-01-01

    Up to now the efficiency of in-service control had been limited and dependent on special qualifications of the super-intending personnel and was thus neither exact nor transferable. In the meantime a great number of testing and measuring facilities for special application have been developed. Even novel types of testing methods do not grant absolutely precise statements. In most cases, however, there is a possibility of planning repairs by trend control and of avoiding failures of operation with aggravating consequences. Technical designers from all subject fields should be made familiar with the continually increasing spectrum of in-service inspection techniques so that a better application of modern and well-tried testing methods can be planned. Systematic in-service inspections complete the Rules of Technology which are safety-oriented with regard to the nonlinear wear between regular dates of control which has been ignored so far and its implied risks. Components which are not liable to control can be checked much better by novel type methods. (orig./RW) [de

  7. Structural and electrochemical properties of single crystalline MoV 2O8 nanowires for energy storage devices

    KAUST Repository

    Shahid, Muhammad; Liu, Jingling; Ali, Zahid; Shakir, Imran; Warsi, Muhammad Farooq

    2013-01-01

    We report the synthesis of MoV2O8 nanowires of high quality using spin coating followed by the thermal annealing process. Transmission electron microscopy (TEM) reveals the average diameter of synthesized nanowire about 100 nm, and average length ranges from 1 to 5 μm. The TEM analysis further confirms the <001> growth direction of MoV 2O8 nanowires. The electrochemical properties of synthesized nanowires using cyclic voltammetry show the specific capacitance 56 Fg-1 at the scan rate of 5 mV s-1 that remains 24 Fg -1 at 100 mV s-1. The electrochemical measurements suggest that the MoV2O8 nanowires can be used as a material for the future electrochemical capacitors (energy storage devices). © 2012 Published by Elsevier Inc. All rights reserved.

  8. Structural and electrochemical properties of single crystalline MoV 2O8 nanowires for energy storage devices

    KAUST Repository

    Shahid, Muhammad

    2013-05-01

    We report the synthesis of MoV2O8 nanowires of high quality using spin coating followed by the thermal annealing process. Transmission electron microscopy (TEM) reveals the average diameter of synthesized nanowire about 100 nm, and average length ranges from 1 to 5 μm. The TEM analysis further confirms the <001> growth direction of MoV 2O8 nanowires. The electrochemical properties of synthesized nanowires using cyclic voltammetry show the specific capacitance 56 Fg-1 at the scan rate of 5 mV s-1 that remains 24 Fg -1 at 100 mV s-1. The electrochemical measurements suggest that the MoV2O8 nanowires can be used as a material for the future electrochemical capacitors (energy storage devices). © 2012 Published by Elsevier Inc. All rights reserved.

  9. Study on Mo(V) species, location and adsorbates interactions in MoH-SAPO-34 by employing ESR and electron spin-echo modulation spectroscopies

    International Nuclear Information System (INIS)

    Back, Gern Ho; Jang, Chang Ki; Ru, Chang Kuk; Cho, Young Hwan; So, Hyun Soo; Larry, Keven

    2002-01-01

    A solid-state reaction of MoO 3 with as-synthesized H-SAPO-34 generated paramagnetic Mo(V) species. The dehydration resulted in weak Mo(V) species, and subsequent activation resulted in the formation of Mo(V) species such as Mo(V) 5c and Mo(V) 6c that are characterized by ESR. The data of ESR and ESEM show the oxomolybdenum species, to be (MoO 2 ) + or (MoO) 3+ . The (MoO 2 ) + species seems to be more probable. Since H-SAPO-34 has a low framework negative charge, (MoO) 3+ with a high positive charge can not be easily stabilized. A solution reaction between the solution of silico-molybdic acid and calcined H-SAPO-34 resulted in only MoO + 2 species. A rhombic ESR signal is observed on adsorption of D 2 O, CD 3 OH, CH 3 CH 2 OD and ND 3 . The Location and coordination structure of Mo(V) species has been determined by three-pulse electron spin-echo modulation data and their simulations. After the adsorption of methanol, ethylene, ammonia, and water for MoH-SAPO-34, three molecules, one and one molecule, respectively, are directly coordinated to (MoO 2 ) +

  10. A practical approach for implementing risk-based inservice testing of pumps at nuclear power plants

    International Nuclear Information System (INIS)

    Hartley, R.S.; Maret, D.; Seniuk, P.; Smith, L.

    1996-01-01

    The American Society of Mechanical Engineers (ASME) Center for Research and Technology Development's (CRTD) Research Task Force on Risk-Based Inservice Testing has developed guidelines for risk-based inservice testing (IST) of pumps and valves. These guidelines are intended to help the ASME Operation and Maintenance (OM) Committee to enhance plant safety while focussing appropriate testing resources on critical components. This paper describes a practical approach for implementing those guidelines for pumps at nuclear power plants. The approach, as described in this paper, relies on input, direction, and assistance from several entities such as the ASME Code Committees, United States Nuclear Regulatory Commission (NRC), and the National Laboratories, as well as industry groups and personnel with applicable expertise. Key parts of the risk-based IST process that are addressed here include: identification of important failure modes, identification of significant failure causes, assessing the effectiveness of testing and maintenance activities, development of alternative testing and maintenance strategies, and assessing the effectiveness of alternative testing strategies with present ASME Code requirements. Finally, the paper suggests a method of implementing this process into the ASME OM Code for pump testing

  11. A practical approach for implementing risk-based inservice testing of pumps at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hartley, R.S. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Maret, D.; Seniuk, P.; Smith, L.

    1996-12-01

    The American Society of Mechanical Engineers (ASME) Center for Research and Technology Development`s (CRTD) Research Task Force on Risk-Based Inservice Testing has developed guidelines for risk-based inservice testing (IST) of pumps and valves. These guidelines are intended to help the ASME Operation and Maintenance (OM) Committee to enhance plant safety while focussing appropriate testing resources on critical components. This paper describes a practical approach for implementing those guidelines for pumps at nuclear power plants. The approach, as described in this paper, relies on input, direction, and assistance from several entities such as the ASME Code Committees, United States Nuclear Regulatory Commission (NRC), and the National Laboratories, as well as industry groups and personnel with applicable expertise. Key parts of the risk-based IST process that are addressed here include: identification of important failure modes, identification of significant failure causes, assessing the effectiveness of testing and maintenance activities, development of alternative testing and maintenance strategies, and assessing the effectiveness of alternative testing strategies with present ASME Code requirements. Finally, the paper suggests a method of implementing this process into the ASME OM Code for pump testing.

  12. Application of risk-based methods to inservice testing of check valves

    Energy Technology Data Exchange (ETDEWEB)

    Closky, N.B.; Balkey, K.R.; McAllister, W.J. [and others

    1996-12-01

    Research efforts have been underway in the American Society of Mechanical Engineers (ASME) and industry to define appropriate methods for the application of risk-based technology in the development of inservice testing (IST) programs for pumps and valves in nuclear steam supply systems. This paper discusses a pilot application of these methods to the inservice testing of check valves in the emergency core cooling system of Georgia Power`s Vogtle nuclear power station. The results of the probabilistic safety assessment (PSA) are used to divide the check valves into risk-significant and less-risk-significant groups. This information is reviewed by a plant expert panel along with the consideration of appropriate deterministic insights to finally categorize the check valves into more safety-significant and less safety-significant component groups. All of the more safety-significant check valves are further evaluated in detail using a failure modes and causes analysis (FMCA) to assist in defining effective IST strategies. A template has been designed to evaluate how effective current and emerging tests for check valves are in detecting failures or in finding significant conditions that are precursors to failure for the likely failure causes. This information is then used to design and evaluate appropriate IST strategies that consider both the test method and frequency. A few of the less safety-significant check valves are also evaluated using this process since differences exist in check valve design, function, and operating conditions. Appropriate test strategies are selected for each check valve that has been evaluated based on safety and cost considerations. Test strategies are inferred from this information for the other check valves based on similar check valve conditions. Sensitivity studies are performed using the PSA model to arrive at an overall IST program that maintains or enhances safety at the lowest achievable cost.

  13. 76 FR 52355 - NUREG-1482, Revision 2, “Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report...

    Science.gov (United States)

    2011-08-22

    ... Testing at Nuclear Power Plants, Draft Report for Comment'' AGENCY: Nuclear Regulatory Commission. ACTION... Testing at Nuclear Power Plants, Draft Report for Comment,'' and subtitled ``Inservice Testing of Pumps... Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants'' is available electronically...

  14. Automatic ultrasonic testing and the LOFT in-service inspection program

    International Nuclear Information System (INIS)

    Hunter, J.A.

    1980-01-01

    An automatic ultrasonic testing system has been developed which significantly improves the flaw indication detection and characterization capability over the capability of conventional volumetric examination techniques. The system utilizes an accurately located ultrasonic sensor to generate the examination data. A small computer performs and integrates control and data input/output functions. Computer software has been developed to provide a rigorous method for data analysis and ultrasonic image interpretation. The system has been used as part of an in-service inspection program to examine welds in thich austenitic stainless steel pipes in a small experimental nuclear reactor

  15. Risk-based inservice testing program modifications at Palo Verde nuclear generating station

    International Nuclear Information System (INIS)

    Knauf, S.; Lindenlaub, B.; Linthicum, R.

    1996-01-01

    Arizona Public Service Company (APS) is investigating changes to the Palo Verde Inservice Testing (IST) Program that are intended to result in the reduction of the required test frequency for various valves in the American Society of Mechanical Engineers (ASME) Section XI IST program. The analytical techniques employed to select candidate valves and to demonstrate that these frequency reductions are acceptable are risk based. The results of the Palo Verde probabilistic risk assessment (PRA), updated in June 1994, and the risk significant determination performed as part of the implementation efforts for 10 CFR 50.65 (the maintenance rule) were used to select candidate valves for extended test intervals. Additional component level evaluations were conducted by an 'expert panel.' The decision to pursue these changes was facilitated by the ASME Risk-Based Inservice Testing Research Task Force for which Palo Verde is participating as a pilot plant. The NRC's increasing acceptance of cost beneficial licensing actions and risk-based submittals also provided incentive to seek these changes. Arizona Public Service is pursuing the risk-based IST program modification in order to reduce the unnecessary regulatory burden of the IST program through qualitative and quantitative analysis consistent with maintaining a high level of plant safety. The objectives of this project at Palo Verde are as follows: (1) Apply risk-based technologies to IST components to determine their risk significance (i.e., high or low). (2) Apply a combination of deterministic and risk-based methods to determine appropriate testing requirements for IST components including improvement of testing methods and frequency intervals for high-risk significant components. (3) Apply risk-based technologies to high-risk significant components identified by the open-quotes expert panelclose quotes and outside of the IST program to determine whether additional testing requirements are appropriate

  16. Risk-based inservice testing program modifications at Palo Verde nuclear generating station

    Energy Technology Data Exchange (ETDEWEB)

    Knauf, S.; Lindenlaub, B.; Linthicum, R.

    1996-12-01

    Arizona Public Service Company (APS) is investigating changes to the Palo Verde Inservice Testing (IST) Program that are intended to result in the reduction of the required test frequency for various valves in the American Society of Mechanical Engineers (ASME) Section XI IST program. The analytical techniques employed to select candidate valves and to demonstrate that these frequency reductions are acceptable are risk based. The results of the Palo Verde probabilistic risk assessment (PRA), updated in June 1994, and the risk significant determination performed as part of the implementation efforts for 10 CFR 50.65 (the maintenance rule) were used to select candidate valves for extended test intervals. Additional component level evaluations were conducted by an `expert panel.` The decision to pursue these changes was facilitated by the ASME Risk-Based Inservice Testing Research Task Force for which Palo Verde is participating as a pilot plant. The NRC`s increasing acceptance of cost beneficial licensing actions and risk-based submittals also provided incentive to seek these changes. Arizona Public Service is pursuing the risk-based IST program modification in order to reduce the unnecessary regulatory burden of the IST program through qualitative and quantitative analysis consistent with maintaining a high level of plant safety. The objectives of this project at Palo Verde are as follows: (1) Apply risk-based technologies to IST components to determine their risk significance (i.e., high or low). (2) Apply a combination of deterministic and risk-based methods to determine appropriate testing requirements for IST components including improvement of testing methods and frequency intervals for high-risk significant components. (3) Apply risk-based technologies to high-risk significant components identified by the {open_quotes}expert panel{close_quotes} and outside of the IST program to determine whether additional testing requirements are appropriate.

  17. Risk-informed inservice test activities at the NRC

    International Nuclear Information System (INIS)

    Fischer, D.; Cheok, M.; Hsia, A.

    1996-01-01

    The operational readiness of certain safety-related components is vital to the safe operation of nuclear power plants. Inservice testing (IST) is one of the mechanisms used by licensees to ensure this readiness. In the past, the type and frequency of IST have been based on the collective best judgment of the NRC and industry in an ASME Code consensus process and NRC rulemaking process. Furthermore, IST requirements have not explicitly considered unique component and system designs and contribution to overall plant risk. Because of the general nature of ASME Code test requirements and non-reliance on risk estimates, current IST requirements may not adequately emphasize testing those components that are most important to safety and may overly emphasize testing of less safety significant components. Nuclear power plant licensees are currently interested in optimizing testing by applying resources in more safety significant areas and, where appropriate, reducing measures in less safety-significant areas. They are interested in maintaining system availability and reducing overall maintenance costs in ways that do not adversely affect safety. The NRC has been interested in using probabilistic, as an adjunct to deterministic, techniques to help define the scope, type and frequency of IST. The development of risk-informed IST programs has the potential to optimize the use of NRC and industry resources without adverse affect on safety

  18. Risk-informed inservice test activities at the NRC

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, D.; Cheok, M.; Hsia, A.

    1996-12-01

    The operational readiness of certain safety-related components is vital to the safe operation of nuclear power plants. Inservice testing (IST) is one of the mechanisms used by licensees to ensure this readiness. In the past, the type and frequency of IST have been based on the collective best judgment of the NRC and industry in an ASME Code consensus process and NRC rulemaking process. Furthermore, IST requirements have not explicitly considered unique component and system designs and contribution to overall plant risk. Because of the general nature of ASME Code test requirements and non-reliance on risk estimates, current IST requirements may not adequately emphasize testing those components that are most important to safety and may overly emphasize testing of less safety significant components. Nuclear power plant licensees are currently interested in optimizing testing by applying resources in more safety significant areas and, where appropriate, reducing measures in less safety-significant areas. They are interested in maintaining system availability and reducing overall maintenance costs in ways that do not adversely affect safety. The NRC has been interested in using probabilistic, as an adjunct to deterministic, techniques to help define the scope, type and frequency of IST. The development of risk-informed IST programs has the potential to optimize the use of NRC and industry resources without adverse affect on safety.

  19. ASME N511-19XX, Standard for periodic in-service testing of nuclear air treatment, heating, ventilating and air conditioning systems

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-08-01

    A draft version of the Standard is presented in this document. The Standard covers the requirements for periodic in-service testing of nuclear safety-related air treatment, heating, ventilating, and air conditioning systems in nuclear facilities. The Standard provides a basis for the development of test programs and does not include acceptance criteria, except in cases where the results of one test influence the performance of other tests. The Standard covers general inspection and test requirements, reference values, inspection and test requirements, generic tests, acceptance criteria, in-service test requirements, testing following an abnormal incident, corrective action requirements, and quality assurance. Mandatory appendices provide a visual inspection checklist and four test procedures. Non-mandatory appendices provide additional information and guidance on mounting frame pressure leak test procedure, corrective action, challenge gas substitute selection criteria, and test program development. 8 refs., 10 tabs.

  20. ASME N511-19XX, Standard for periodic in-service testing of nuclear air treatment, heating, ventilating and air conditioning systems

    International Nuclear Information System (INIS)

    1997-01-01

    A draft version of the Standard is presented in this document. The Standard covers the requirements for periodic in-service testing of nuclear safety-related air treatment, heating, ventilating, and air conditioning systems in nuclear facilities. The Standard provides a basis for the development of test programs and does not include acceptance criteria, except in cases where the results of one test influence the performance of other tests. The Standard covers general inspection and test requirements, reference values, inspection and test requirements, generic tests, acceptance criteria, in-service test requirements, testing following an abnormal incident, corrective action requirements, and quality assurance. Mandatory appendices provide a visual inspection checklist and four test procedures. Non-mandatory appendices provide additional information and guidance on mounting frame pressure leak test procedure, corrective action, challenge gas substitute selection criteria, and test program development. 8 refs., 10 tabs

  1. Development of in-service inspection system for core support graphite structures in the high temperature engineering test reactor (HTTR)

    Energy Technology Data Exchange (ETDEWEB)

    Sumita, Junya; Hanawa, Satoshi; Kikuchi, Takayuki; Ishihara, Masahiro [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    2003-03-01

    Visual inspection of core support graphite structures using TV camera as in-service inspection and measurement of material characteristics using surveillance test specimens are planned in the High Temperature Engineering Test Reactor (HTTR) to confirm structural integrity of the core support graphite structures. For the visual inspection, in-service inspection system developed from September 1996 to June 1998, and pre-service inspection using the system was carried out. As the result of the pre-service inspection, it was validated that high quality of visual inspection with TV camera can be carried out, and also structural integrity of the core support graphite structures at the initial stage of the HTTR operation was confirmed. (author)

  2. 78 FR 71676 - NUREG-1482, Revision 2, “Guidelines for Inservice Testing at Nuclear Power Plants, Final Report”

    Science.gov (United States)

    2013-11-29

    ... Testing at Nuclear Power Plants, Final Report'' AGENCY: Nuclear Regulatory Commission. ACTION: Notice of... entitled: NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at Nuclear Power Plants,'' and... Restraints (Snubbers) at Nuclear Power Plants.'' In the previous Revisions 0 and 1 of NUREG-1482, the NRC...

  3. Evaluation of inservice inspection examinatiions

    International Nuclear Information System (INIS)

    Aldrich, D.A.; Cook, J.F.

    1990-05-01

    In order to evaluate the effectiveness of Section 11, Division 1, ''Rules for Inservice Inspection of Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code examinations, 26 inservice inspection (ISI) summary reports from 24 facilities were reviewed. It was found that these ASME Code examinations and tests are instrumental in revealing indications and defects in welds and plant components. In addition, this study uncovered that fact that some of the Section 11 requirements are apparently not clear and are misunderstood by some of the facilities. Also, the need for more stringent requirements was evaluated and some Code changes are recommended

  4. Review of Section XI inservice inspection program effectiveness

    International Nuclear Information System (INIS)

    Cook, J.F. Sr.

    1993-08-01

    To evaluate the effectiveness of Section XI, Division 1, open-quotes Rules for Inservice Inspection of Nuclear Power Plant Components,close quotes of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, searches were performed of the Licensing Event Report and Nuclear Plant Reliability Data System computerized data bases, and a review was made of inservice inspection summary reports. It was found that the Section XI examinations and tests detect flaws in welds and plant components and result in subsequent corrective action. This study also shows that the format and topics of information provided in Section XI-prescribed inservice inspection summary reports vary widely

  5. Review of Section XI inservice inspection program effectiveness

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.F. Sr.

    1993-08-01

    To evaluate the effectiveness of Section XI, Division 1, {open_quotes}Rules for Inservice Inspection of Nuclear Power Plant Components,{close_quotes} of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, searches were performed of the Licensing Event Report and Nuclear Plant Reliability Data System computerized data bases, and a review was made of inservice inspection summary reports. It was found that the Section XI examinations and tests detect flaws in welds and plant components and result in subsequent corrective action. This study also shows that the format and topics of information provided in Section XI-prescribed inservice inspection summary reports vary widely.

  6. A Methodology for Evaluation of Inservice Test Intervals for Pumps and Motor Operated Valves

    International Nuclear Information System (INIS)

    McElhaney, K.L.

    1999-01-01

    The nuclear industry has begun efforts to reevaluate inservice tests (ISTs) for key components such as pumps and valves. At issue are two important questions--What kinds of tests provide the most meaningful information about component health, and what periodic test intervals are appropriate? In the past, requirements for component testing were prescribed by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. The tests and test intervals specified in the Code were generic in nature and test intervals were relatively short. Operating experience has shown, however, that performance and safety improvements and cost savings could be realized by tailoring IST programs to similar components with comparable safety importance and service conditions. In many cases, test intervals may be lengthened, resulting in cost savings for utilities and their customers

  7. Epitaxial (100)-oriented Mo/V superlattice grown on MgO(100) by dcMS and HiPIMS

    International Nuclear Information System (INIS)

    Shayestehaminzadeh, S.; Magnusson, R.L.; Gislason, H.P.; Olafsson, S.

    2013-01-01

    Epitaxial (100)-oriented Mo/V superlattices have been grown by High Power Impulse Magnetron Sputtering (HiPIMS) and dc Magnetron Sputtering (dcMS) on single-crystalline MgO(100) substrates at growth temperatures ranging from 30 °C to 600 °C. Superlattice bilayer period of Mo/V around 12/12 monolayers and 15 repeat periods was studied. This study aims to investigate the effect of the HiPIMS process on reducing the growth temperature of Mo/V superlattices using the high energy ionized Mo, V species in the HiPIMS plasma. In one case, the Mo layer was only grown with the HiPIMS process and V layer grown using the dcMS process while in another both layers were grown with the HiPIMS process. The as-deposited films were characterized by X-ray reflection and diffraction techniques. The dcMS process was found to give superior superlattice growth at high growth temperatures while a mixed Mo HiPIMS and V dcMS process gives better result at lower growth temperatures (300 °C). Room temperature growth reveals that neither the mixed Mo HiPIMS and V dcMS process nor the pure HiPIMS for both materials can produce better result compared to the pure dcMS process, which gives a relatively better result. - Highlights: • Epitaxial (100)-oriented Mo/V superlattices have been grown by HiPIMS and dcMS on MgO(100) for various temperatures. • The study was aimed to investigate the effect of ionized HiPIMS process onlowering the growth temperature. • The dcMS process was found to give superior superlattice growth at high growth temperature. • The mixed Mo HiPIMS and V dcMS process gives best result at lower growth temperatures

  8. In-service inspection program for the NCS-80 reactor pressure vessel

    International Nuclear Information System (INIS)

    Scharge, J.; Wehowsky, P.; Zeibig, H.

    1978-01-01

    The in-service inspection program of reactor pressure vessels is mainly based on the ultra-sonic method, visual checking of inner and outer surfaces as well as pressure and leak tests. The test procedure require a design of the pressure vessel suitable for the test methods and the possibility to remove the pressure vessel internals. For the outside inspection a gap of sufficient width is mandatory. The present status of the ultra-sonic method and of the inner and outer manipulators affords to conduct the in-service inspection program in form of automatic checkings. The in-service inspection program for NCS-80, the Nuclear Container-Ship design of 80,000 shp, is integrated in the refueling periods due to the request for a high availability of the ship and reactor plant

  9. Application of signature analysis for determining the operational readiness of motor-operated valves under blowdown test conditions

    International Nuclear Information System (INIS)

    Haynes, H.D.

    1990-01-01

    In support of the NRC-funded Nuclear Plant Aging Research (NPAR) program, Oak Ridge National Laboratory (ORNL) has carried out a comprehensive aging assessment of motor-operated valves (MOVs). As part of this work, ORNL participated in the gate valve flow interrruption blowdown (GVFIB) tests carried out in Huntsville, Alabama. The tests provided an excellent opportunity to evaluate signature analysis methods for determining the operability of MOVs under accident conditions. ORNL acquired motor current and torque switch shaft angular position signatures on two test MOVs during several GVFIB tests. The reduction in operating ''margin'' of both MOVs due to the presence of additional valve running loads imposed by high flow was clearly observed in motor current and torque switch angular position signatures. In addition, the effects of differential pressure, fluid temperature, and line voltage on MOV operations were observed and more clearly understood as a result of utilizing the signature analysis techniques. (orig.)

  10. Spectral Filtering Criteria for U-Band Test Light for In-Service Line Monitoring in Optical Fiber Networks

    Science.gov (United States)

    Honda, Nazuki; Izumita, Hisashi; Nakamura, Minoru

    2006-06-01

    In the fiber-to-the-home era, thousands of optical fibers will have to be accommodated in the central offices of optical access networks. To reduce maintenance costs and improve the service reliability of optical fiber networks, the authors must develop an optical fiber line testing system with a function for in-service line monitoring that uses a test light with a wavelength different from the communication light wavelength. To monitor an in-service line in an optical network, the effective rejection ratio of the test light must be taken into account. This ratio depends on the spectrum of the test light from the optical time-domain reflectometer and the rejection band of the filter in front of the optical network unit. The dependence of the effective rejection ratio as a function of the sideband suppression ratio (SBSR) and of the ratio of the rejection band to the bandwidth of the sideband noise d/D is clarified. When d/D =0.1 and the target effective rejection ratio of the filter is -40 dB, the SBSR and the filter loss of the termination cable must be -70 and -43 dB, respectively, or the SBSR must be -80 dB. When d/D service line monitoring for a 10-Gb/s transmission using a 1650-nm test light with an SBSR of -80 dB is also demonstrated.

  11. Non-destructive inservice inspections

    International Nuclear Information System (INIS)

    Kauppinen, P.; Sarkimo, M.; Lahdenperae, K.

    1998-01-01

    In order to assess the possible damages occurring in the components and structures of operating nuclear power plants during service the main components and structures are periodically inspected by non-destructive testing techniques. The reliability of non-destructive testing techniques applied in these inservice inspections is of major importance because the decisions concerning the needs for repair of components are mainly based on the results of inspections. One of the targets of this research program has been to improve the reliability of non-destructive testing. This has been addressed in the sub-projects which are briefly summarised here. (author)

  12. Review of inservice inspection and nondestructive examination practices at DOE Category A test and research reactors

    International Nuclear Information System (INIS)

    Anderson, M.T.; Aldrich, D.A.

    1990-09-01

    In-service inspection (ISI) programs are used at commercial nuclear power plants for monitoring the pressure boundary integrity of various systems and components to ensure their continued safe operation. The Department of Energy (DOE) operates several test and research reactors. This report represents an evaluation of the ISI and nondestructive examination (NDE) practices at five DOE Category A (> 20 MW thermal) reactors as compared, where applicable, to the current ISI activities of commercial nuclear power facilities. The purpose of an inservice inspection (ISI) program is to establish regular surveillance of safety-related components to ensure their safe and reliable operation. The integrity of materials comprising these components is generally monitored by means of periodic nondestructive examinations (NDE), which, if appropriately performed, provide methods for identifying degradation that could render components unable to perform their intended safety functions. The reactors evaluated during this review were the Experimental Breeder Reactor 2 and the Fast Flux Test Facility (liquid-metal cooled plants), the Advanced Test Reactor and the High Flux Isotopes Reactor (light-water cooled reactors), and the High Flux Beam Reactor (a heavy-water cooled facility). Although these facilities are extremely diverse in design and operation, they all have less stored energy, smaller inventories of radionuclides, and generally, more remote locations than commercial reactors. However, all DOE test and research facilities contain components similar to those of commercial reactors for which continued integrity is important to maintain plant safety. 10 refs., 6 tabs

  13. Laurels for Swiss in-service inspection team

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    Following what is believed to be the first successful application of P-scan ultrasonic testing for the in-service inspection of austenitic welds in the boiling water reactor at Wuergassen (Federal Republic of Germany) last year, Sulzer participated in a 'round robin' test organized by the Electric Power Research Institute in the USA form May to July 1983. (Auth.)

  14. Application of signature analysis for determining the operational readiness of motor-operated valves under blowdown test conditions

    International Nuclear Information System (INIS)

    Haynes, H.D.

    1988-01-01

    In support of the NRC-funded Nuclear Plant Aging Research (NPAR) program, Oak Ridge National Laboratory (ORNL) has carried out a comprehensive aging assessment of Motor-Operated Valves (MOVs). As part of this work, ORNL participated in the Gate Valve Flow Interruption Blowdown (GVFIB) tests carried out in Huntsville, Alabama. The GVFIB tests were intended primarily to determine the behavior of motor-operated gate valves under the temperature, pressure, and flow conditions expected to be experienced by isolation valves in Boiling Water Reactors (BWRs) during a high energy line break (blowdown) outside of containment. In addition, the tests provided an excellent opportunity to evaluate signature analysis methods for determining the operational readiness of the MOVs under those accident conditions. ORNL acquired motor current and torque switch shaft angular position data on two test MOVs during various times of the GVFIB tests. The reduction in operating ''margin'' of both MOVs due to the presence of additional valve running loads imposed by high flow was clearly observed in motor current and torque switch angular position signatures. In addition, the effects of differential pressure, fluid temperature, and line voltage on MOV operations were observed and more clearly understood as a result of utilizing signature analysis techniques. 1 ref.; 16 figs

  15. In-service inspection for nuclear power plants

    International Nuclear Information System (INIS)

    1980-01-01

    The Safety Guides are recommendations issued by the Agency for use by Member States in the context of their own nuclear safety requirements. Design consideration, in-service examination, test requirements, repair and replacement, equipment, methods and techniques and also administrative aspects are given in this issue

  16. Multi-Canister overpack inservice inspection and maintenance

    International Nuclear Information System (INIS)

    SMITH, K.E.

    1998-01-01

    The factors to be considered in establishing inservice inspection and maintenance requirements for the Multi-Canister Overpack (MCO) include evaluating the likelihood of degradation to the MCO pressure boundary due to erosion and corrosion, reviewing commercial practice for NRC licensed spent nuclear fuel storage systems, and examining the individual MCO components for maintenance needs. Reviews of the potential for MCO erosion and corrosion conclude that neither will pose a threat to the MCO pressure boundary. Consistent with commercial practice for spent fuel storage systems, the MCO closure weld will be helium leak tested prior to placement in interim storage. Beyond the CSB facility related monitoring plans (radiological monitoring, emissions monitoring, vault cooling data, etc.), no inservice inspection or maintenance of the MCO is required during interim storage

  17. In-service inspections of the reactor cooling system of pressurized water reactors

    International Nuclear Information System (INIS)

    Fuerste, W.; Hohnerlein, G.; Werden, B.

    1982-01-01

    In order to guarantee constant safety of the components of the reactor cooling system, regular in-service inspections are carried out after commissioning of the nuclear power plant. This contribution is concerned with the components of the reactor cooling system, referring to the legal requirements, safety-related purposes and scope of the in-service inspections during the entire period of operation of a nuclear power plant. Reports are made with respect to type, examination intervals, examination technique, results and future development. The functional tests which are carried out within the scope of the in-service inspections are not part of this contribution. (orig.) [de

  18. Characterization on the Microstructure Evolution and Toughness of TIG Weld Metal of 25Cr2Ni2MoV Steel after Post Weld Heat Treatment

    Directory of Open Access Journals (Sweden)

    Xia Liu

    2018-03-01

    Full Text Available The microstructure and toughness of tungsten inert gas (TIG backing weld parts in low-pressure steam turbine welded rotors contribute significantly to the total toughness of the weld metal. In this study, the microstructure evolution and toughness of TIG weld metal of 25Cr2Ni2MoV steel low-pressure steam turbine welded rotor under different post-weld heat treatment (PWHT conditions are investigated. The fractography and microstructure of weld metal after PWHT are characterized by optical microscope, SEM, and TEM, respectively. The Charpy impact test is carried out to evaluate the toughness of the weld. The optical microscope and SEM results indicate that the as-welded sample is composed of granular bainite, acicular ferrite and blocky martensite/austenite (M-A constituent. After PWHT at 580 °C, the blocky M-A decomposes into ferrite and carbides. Both the number and size of precipitated carbides increase with holding time. The impact test results show that the toughness decreases dramatically after PWHT and further decreases with holding time at 580 °C. The precipitated carbides are identified as M23C6 carbides by TEM, which leads to the dramatic decrease in the toughness of TIG weld metal of 25Cr2Ni2MoV steel.

  19. In-service inspections of V-230 reactor

    International Nuclear Information System (INIS)

    Prepechal, J.

    1984-01-01

    It is stated that despite certain constraints the configuration of the WWER-440 is such that it allows to make in-service inspections on a fully satisfactory scale. Three factors are discussed whose existence is necessary for the implementation of in-service inspections. The program defining the scale of inspections is satisfactory with regard to the safety and reliability of reactor operation. Its further development must result in reducing time consumption and radiation burden of personnel. Regulations for the implementation and evaluation of inspections represent the weakest link in the system of in-service inspections. At present, various organizations are dealing with the said problem within international cooperation. Equipment for in-service inspections of WWER-440 reactors is relatively good. The most important knowledge is summed up gained from the ten pre-service and in-service inspections of reactors of this type made so far. (Z.M.)

  20. Motor current signature analysis for determining operational readiness of motor-operated valves (MOVs)

    International Nuclear Information System (INIS)

    Kryter, R.C.; Haynes, H.D.

    1987-01-01

    Motor current signature analysis (MCSA) is a novel diagnostic process for condition monitoring of electric-motor-driven mechanical equipment (e.g., pumps, motor-operated valves, compressors, and processing machinery). The MCSA process identifies, characterizes, and trends over time the instantaneous load variations of mechanical equipment in order to diagnose changes in the condition of the equipment (e.g., due to degradation or service wear), which, if allowed to continue, may lead to failure. It monitors the instantaneous variations (noise content) in the electric current flowing through the power leads to the electric motor that drives the equipment. The motor itself thereby acts as a transducer, sensing both large and small, long-term and rapid, mechanical load variations and converting them to variations in the induced current generated in the motor windings. This motor current noise signature is detected, amplified, and further processed as needed to examine its time domain and frequency domain (spectral) characteristics. The operational principles of MCSA and the nonintrusive data collection apparatus and procedure used with MOVs will be described. Data collected from MOVs in both laboratory and in-plant environments will also be shown to illustrate the ability of MCSA to ''see'' the detailed inner workings of the valve and operator and thus to detect degraded performance at an incipient stage. (Set of 18 vugraphs)

  1. Importance Analysis of In-Service Testing Components for Ulchin Unit 3

    International Nuclear Information System (INIS)

    Dae-Il Kan; Kil-Yoo Kim; Jae-Joo Ha

    2002-01-01

    We performed an importance analysis of In-Service Testing (IST) components for Ulchin Unit 3 using the integrated evaluation method for categorizing component safety significance developed in this study. The importance analysis using the developed method is initiated by ranking the component importance using quantitative PSA information. The importance analysis of the IST components not modeled in the PSA is performed through the engineering judgment, based on the expertise of PSA, and the quantitative and qualitative information for the IST components. The PSA scope for importance analysis includes not only Level 1 and 2 internal PSA but also Level 1 external and shutdown/low power operation PSA. The importance analysis results of valves show that 167 (26.55%) of the 629 IST valves are HSSCs and 462 (73.45%) are LSSCs. Those of pumps also show that 28 (70%) of the 40 IST pumps are HSSCs and 12 (30%) are LSSCs. (authors)

  2. Nuclear power plant pressure vessels. Inservice inspections

    International Nuclear Information System (INIS)

    1995-01-01

    The requirements for the planning and reporting of inservice inspections of nuclear power plant pressure vessels are presented. The guide specifically applies to inservice inspections of Safety class 1 and 2 nuclear power plant pressure vessels, piping, pumps and valves plus their supports and reactor pressure vessel internals by non- destructive examination methods (NDE). Inservice inspections according to the Pressure Vessel Degree (549/73) are discussed separately in the guide YVL 3.0. (4 refs.)

  3. Psychodrama Techniques for Inservice Teacher Training

    Science.gov (United States)

    Kohut, Sylvester, Jr.

    1976-01-01

    By using psychodrama techniques in inservice programming, improvement in communication among members of the school community occurs. With modification the psychodrama approach can be used with inservice teachers and administrators to improve self-realization and communication. A program using psychodrama techniques is described in the article.…

  4. Effect of laser absorption on picosecond laser ablation of Cr12MoV mold steel, 9Cr18 stainless steel and H13A cemented carbide

    Science.gov (United States)

    Wu, Baoye; Liu, Peng; Wang, Xizhao; Zhang, Fei; Deng, Leimin; Duan, Jun; Zeng, Xiaoyan

    2018-05-01

    Due to excellent properties, Cr12MoV mold steel, 9Cr18 stainless steel and H13A cemented carbide are widely used in industry. In this paper, the effect of absorption of laser light on ablation efficiency and roughness have been studied using a picosecond pulse Nd:YVO4 laser. The experimental results reveal that laser wavelength, original surface roughness and chemical composition play an important role in controlling ablation efficiency and roughness. Firstly, higher ablation efficiency with lower surface roughness is achieved on the ablation of 9Cr18 at 532, comparing with 1064 nm. Secondly, the ablation efficiency increases while the Ra of the ablated region decreases with the decrease of original surface roughness on ablation of Cr12MoV mold steel at 532 nm. Thirdly, the ablation efficiency of H13A cemented carbide is much higher than 9Cr18 stainless steel and Cr12MoV mold steel at 1064 nm. Scanning electron microscopy images reveals the formation of pores on the surface of 9Cr18 stainless steel and Cr12MoV mold steel at 532 nm while no pores are formed at 1064 nm. As to H13A cemented carbide, worm-like structure is formed at 1064 nm. The synergetic effects of the heat accumulation, plasma shielding and ablation threshold on laser ablation efficiency and machining quality were analyzed and discussed systematically in this paper.

  5. ASME section XI: rules for inservice inspection of nuclear power plants -an introspection

    Energy Technology Data Exchange (ETDEWEB)

    John, P K; Anto, Y; Mungikar, C P; Wagh, P M [Nuclear Power Corporation of India Ltd., Tarapur (India). Tarapur Atomic Power Station

    1994-12-31

    Section XI of the ASME BPV code is addressed to the examination, test and inspection requirements of the components of nuclear power plants (NPPs). Since its inception in 1970, this code section has undergone vast changes -probably the most among other ASME BPV code sections. Section XI is full fledged and lays down requirements with regard to all preservice inspections, inservice inspection, repair and replacement of components, tests of system etc. Tarapur Atomic Power Station (TAPS) has the distinction of being one of the earliest BWR type NPPs in the world that has an inservice inspection programme organised in line with the ASME section XI requirements. This paper summarises the experiences gained from time to time using this code section and a few suggestions to prospective users. An effort is also made to explain the philosophy of inservice inspection from ASME section XI point of view. 3 refs.

  6. ASME section XI: rules for inservice inspection of nuclear power plants -an introspection

    International Nuclear Information System (INIS)

    John, P.K.; Anto, Y.; Mungikar, C.P.; Wagh, P.M.

    1994-01-01

    Section XI of the ASME BPV code is addressed to the examination, test and inspection requirements of the components of nuclear power plants (NPPs). Since its inception in 1970, this code section has undergone vast changes -probably the most among other ASME BPV code sections. Section XI is full fledged and lays down requirements with regard to all preservice inspections, inservice inspection, repair and replacement of components, tests of system etc. Tarapur Atomic Power Station (TAPS) has the distinction of being one of the earliest BWR type NPPs in the world that has an inservice inspection programme organised in line with the ASME section XI requirements. This paper summarises the experiences gained from time to time using this code section and a few suggestions to prospective users. An effort is also made to explain the philosophy of inservice inspection from ASME section XI point of view. 3 refs

  7. Preliminary assessment of valve IST effectiveness

    International Nuclear Information System (INIS)

    Grove, E.; DiBiasio, A.; Carbonaro, J.

    1994-01-01

    A preliminary review of inservice testing effectiveness for Code Class 1,2, and 3 valves at nuclear power plants was performed. These requirements are specified by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, and the Operations and Maintenance Standard. The Institute of Nuclear Power Operations Nuclear Plant Reliability Data System (NPRDS) database was used to provide failure reports for these components for 1988 to 1992. This time period coincides with the issuance of Generic Letter 89-04, which resulted in a more consistent application of the requirements by the licensees. For this time period, 8,593 valve failures were identified. From the review of the NPRDS database, the primary failure causes and failure modes for motor-operated valves (MOV), air-operated valves (AOV), and check valves (CV) were identified. Solenoid-operated valves were not reviewed in this study. Plant testing programs were effective in identifying approximately 60% of the CV failures, 46% of the AOV failures, and 44% of the MOV failures

  8. In-service inspection of nuclear power-plant pressure components

    International Nuclear Information System (INIS)

    Lautzenheiser, C.E.

    1976-01-01

    The early light-water-reactor systems for production of commercial power were designed and fabricated in accordance with the codes then being used for fossil-fired power-generating stations with some design changes for increased inspectability during fabrication. Over the past few years, major strides have been made in in-service inspection technology. Work has been under way to determine the reliability of nondestructive testing methods and to develop formal inspection programs throughout the world. The major problems associated with in-service inspection are the scarcity of qualified personnel, the variability in procedures and data recording between inspection agencies, and exposure of inspection personnel to radiation. Further work will be required to more completely mechanize piping inspections to reduce radiation exposure and to standardize inspection procedures, equipment, and certification of personnel. Worldwide attention to the requirements of the American Society of Mechanical Engineers' Boiler and Pressure Vessel Code, the size and integrity of inspection agencies, and efforts such as the development of personnel qualification and certification guides emphasize the importance of in-service inspection to nuclear safety

  9. Systémová dynamika a její modely jako součást Competitive Intelligence

    Directory of Open Access Journals (Sweden)

    Stanislava Mildeová

    2014-12-01

    Full Text Available Obchodní konkurence je oblast, která zatím plně nevyužívá výhod modelování a simulace. V reakci na tento fakt je cílem článku ukázat model simulující konkurenční boj. Model, vycházející z logiky Systémové dynamiky, slouží ke zkoumání efektu vývoje produktů na konkurenceschopnost podniku. V rámci tvorby tohoto vlastního modelu a provedených experimentů autor dokazuje, že použití modelování a simulací je užitečné při získávání nových informací, které nejsou obsaženy v podnikových informačních systémech. I když je prezentovaný model zjednodušením skutečného trhu, takový systémový model může být perspektivním nástrojem Competitive Intelligence.

  10. EPRI flow-loop/in situ test program for motor-operated valves

    International Nuclear Information System (INIS)

    Hosler, J.F.; Dorfman, L.S.

    1994-01-01

    The Electric Power Research Institute is undertaking a comprehensive research program to develop and validate methods for predicting the performance of common motor-operated gate, global, and butterfly valves. To assess motor-operated valve (MOV) performance characteristics and provide a basis for methods validation, full-scale testing was conducted on 62 MOVs. Tests were performed in four flow-loop facilities and in nine nuclear units. Forty-seven gate, five globe, and 10 butterfly valves were tested under a wide range of flow and differential pressure conditions. The paper describes the test program scope, test configurations, instrumentation and data acquisition, testing approach, and data analysis methods. Key results are summarized

  11. Report on the Regulatory Experience of Risk-Informed In-service Inspection of Nuclear Power Plant Components and Common Views (consensus document)

    International Nuclear Information System (INIS)

    2004-08-01

    The present report represents the work product of the activities conducted by the Task Force. The TF performed a review and inventory of the existing approaches to risk-informed inservice inspection and testing, and completed its work in 1999 with a Current Practices Document 2, titled Report on risk-informed in-service inspection and in-service testing (EUR 19153 EN). In November 2001, the NRWG held a Special session on risk-informed applications, with emphasis on risk-informed inservice inspection, where results and experiences from pilot studies on risk-informed inservice inspection (RI-ISI), performed in several European countries, were presented and discussed. As a follow-up in May 2002, the TF was reconvened with the objectives to analyse from the regulatory point of view key aspects associated with the application of risk-informed inservice inspection, and to go beyond a state of the art report, presenting a series of recommendations of good practices or common positions reached by the regulators represented in the Task Force. (author)

  12. Characterization by notched and precracked Charpy tests of the in-service degradation of RPV steel fracture toughness

    International Nuclear Information System (INIS)

    Fabry, A.

    1997-01-01

    The current engineering and regulatory practice to estimate fracture toughness safety margins for nuclear reactor pressure vessels (RPVs) relies heavily on the CVN impact test. Techniques to estimate in-service toughness degradation directly using a variety of precracked specimens are under development worldwide. Emphasis is on their miniaturization. In the nuclear context, it is essential to address many issues such as representativity of the surveillance programs with respect to the vessel in terms of materials and environment, transferability of test results to the structure (constraint and size effects), lower bound toughness certification, creadibility relative to trends of exising databases. An enhanced RPV surveillance strategy in under development in Belgium. It combines state-of-the-art micromechanical and damage modelling to the evaluation of CVN load-deflection signals, tensile stress-strain curves and slow-bend tests of reconstituted precracked Charpy specimens. A probabilistic micromechanical model has been established for static and dynamic transgranular cleavage initiation fracture toughness in the ductile-brittle transition temperature range. This model allows to project toughness bounds for any steel embrittlement condition from the corresponding CVN and static tensile properties, using a single scaling factor defined by imposing agreement with toughness tests in a single condition. The outstanding finding incorporated by this toughness transfer model is that the microcleavage fracture stress is affected by temperature in the ductile-brittle transition and that this influence is strongly correlated to the flow stress: this explains the shape of the K Ic n K Id temperature curves as well as the actual magnitude of the strain rate and irradiation effects. Furthermore, CVN crack arrest loads and fracture appearance are also taken advantage of in order to estimate K Ia degradation. Finally, the CVN-tensile load-temperature diagram provides substantial

  13. Study on In-Service Inspection Program and Inspection Technologies for Commercialized Sodium-Cooled Fast Reactor

    International Nuclear Information System (INIS)

    Masato Ando; Shigenobu Kubo; Yoshio Kamishima; Toru Iitsuka

    2006-01-01

    The objective of in-service inspection of a nuclear power plant is to confirm integrity of function of components necessary to safety, and satisfy the needs to protect plant investment and to achieve high plant ability. The sodium-cooled fast reactor, which is designed in the feasibility study on commercialized fast reactor cycle systems in Japan, has two characteristics related to in-service inspection. The first is that all sodium coolant boundary structures have double-wall system. Continuous monitoring of the sodium coolant boundary structures are adopted for inspection. The second characteristic is the steam generator with double-wall-tubes. Volumetric testing is adopted to make sure that one of the tubes can maintain the boundary function in case of the other tube failure. A rational in-service inspection concept was developed taking these features into account. The inspection technologies were developed to implement in-service inspection plan. The under-sodium viewing system consisted of multi ultrasonic scanning transducers, which was used for imaging under-sodium structures. The under-sodium viewing system was mounted on the under-sodium vehicle and delivered to core internals. The prototype of under-sodium viewing system and vehicle were fabricated and performance tests were carried out under water. The laboratory experiments of volumetric testing for double-wall-tubes of steam generator, such as ultrasonic testing and remote-field eddy current testing, were performed and technical feasibility was assessed. (authors)

  14. Development, design, construction and testing of pumps, intermediate heat exchangers and manipulator systems for in-service inspection of SNR 300

    International Nuclear Information System (INIS)

    Vroom, J.P.; Heslenfeld, M.W.; Westerweele, W.J.; Willigen, A. van

    1978-01-01

    The first part of this paper reviews the development, design, construction and testing of sodium pumps and intermediate heat exchangers as carried out by NERATOOM in the Netherlands. Testing of full-size components under operational conditions yielded important information for the design of the components for SNR 300. Information is also given in brief on the manufacture of the components. The second part reviews the work done on manipulator systems for in-service inspection as carried out by INTERATOM in Germany. In this field again experience gained from tests had important consequences for the design of the apparatus for SNR 300. (author)

  15. Use of a valve operation test and evaluation system to enhance valve reliability

    International Nuclear Information System (INIS)

    Lowry, D.A.

    1990-01-01

    Power plant owners have emphasized the need for assuring safe, reliable operation of valves. While most valves must simply open or close, the mechanisms involved can be quite complex. Motor operated valves (MOVs) must be properly adjusted to assure operability. Individual operator components determine the performance of the entire MOV. Failure in MOVs could cripple or shut down a unit. Thus, a complete valve program consisting of design reviews, operational testing, and preventive and predictive maintenance activities will enhance an owner's confidence level that his valves win operate as expected. Liberty's Valve Operation Test and Evaluation System (VOTES) accurately measures stein thrust without intruding on valve operation. Since mounting a strain gage to a valve stem is a desirable but impractical way of obtaining precise stem thrust, Liberty developed a method to obtain identical data by placing a strain gage sensor on the valve yoke. VOTES provides information which effectively eliminates costly, unscheduled downtime. This paper presents the results of infield VOTES testing. The system's proven ability to identify and characterize actuator and valve performance is demonstrated. Specific topics of discussion include the ability of VOTES to ease a utility's IE Bulletin 8543 concerns and conclusively diagnose MOV components. Data from static and differential pressure testing are presented. Technical, operational, and financial advantages resulting from VOTES technology are explored in detail

  16. Evaluation of the material in creep-exposed critical 12Cr-1Mo-V ferritic steel components of the pressure section of power plant steam boilers

    International Nuclear Information System (INIS)

    Dobrzanski, J.

    2002-01-01

    Metallographic examinations were carried out on ferritic 12Cr-1Mo-V steel with tempered martensite structure after 68,000 - 145,000 hr service in creep conditions. Structural evolution related to the form of martensite, carbide precipitation and internal damage due to long-term action of thermally activated processes was discussed. A generalised scheme of structural evolution and progress of the internal damage was developed in correlation with the life exhaustion ratio. Principles of the classification for ferritic 12Cr-1Mo-V steel after long-term-service were proposed together with the method for evolution of the state of the material for the industrial practice. (author)

  17. Komunikace závěrů auditu IT procesu prostřednictvím nástrojů systémového myšlení

    Directory of Open Access Journals (Sweden)

    Martin Dalihod

    2014-12-01

    Full Text Available Cílem článku je analyzovat výhody použití nástrojů systémového myšlení při sdělování výsledků interního auditu komunikované auditorem směrem k managementu. Audit je chápán jako nezávislá, objektivní a poradenská činnost, určená pro vytvoření přidané hodnoty a zdokonalování procesů v organizaci. V tomto rámci je navržen systémový archetyp jako obecný model kauzálních smyček a na jeho základě následně vytvořen systémově dynamický model stavů a toků, jenž je aplikovatelný pro účely auditu všech procesů "osvědčených postupů" COBIT. Systémovým přístupem v rámci COBIT autor ilustruje možnost ukázat jiný pohled než je tomu u tradičních lineárních přístupů, kterými nelze zcela vyřešit dlouhodobé problémy v oblasti interního auditu.

  18. The scheme optimization and management innovation for the first containment integrated in-service test of nuclear power plant

    International Nuclear Information System (INIS)

    Wang Haiwei; Yang Gang

    2014-01-01

    The containment integrated test is a large-scale, high risk and very difficult test in pressurized water reactor nuclear power plants. By simulating peak pressure inside the containment in DESIGN-BASIS accident conditions, measuring the total leakage rate of the containment with the peak pressure, and implementing the structure inspection test on several pressure levels, the containment's performance can be verified. Containment integrated test is an important witness point supervised by NNSA. The test results crucially decide the reactor to be started or not. The containment integrated test in 301 overhaul is the first in-service test of Unit 3. By the experience of the same 6 former tests in Qinshan Second Nuclear Power Plant and the feedback from other plants, the test scheme get more scientific and the organization management more standardized. This article discusses the containment integrated test in 301 overhaul and summarizes the experience to provide some references for the following containment integrated tests in the future. (authors)

  19. Examples, clarifications, and guidance on preparing requests for relief from pump and valve inservice testing requirements

    International Nuclear Information System (INIS)

    Ransom, C.B.; Hartley, R.S.

    1996-02-01

    In this report, the Idaho National Engineering Laboratory reviewers discuss related to requests for relief from the American Society of Mechanical Engineers code requirements for inservice testing (IST) of safety-related pumps and valves at commercial nuclear power plants. This report compiles information and examples that may be useful to licensees in developing relief requests submitted to US Nuclear Regulatory Commission (NRC) for their consideration and provides insights and recommendations on related IST issues. The report also gives specific guidance on relief requests acceptable and not acceptable to the NRC and advises licensees in the use of this information for application at their facilities

  20. Appraisal of in-service trainee teachers' competency on applications ...

    African Journals Online (AJOL)

    Most procedures used to obtain information about student learning are subsumed under assessment. This study appraised in-service trainee teachers' competency on applications of principles of test items writing. One Study Centre was purposively drawn from the National Teachers' Institute for the study. A sample of 33 ...

  1. Study on in-service visual inspection using TV camera for core support graphite components in the HTTR

    International Nuclear Information System (INIS)

    Ishihara, Masahiro; Shibata, Taiju; Kikuchi, Takayuki; Mogi, Haruyoshi

    1999-01-01

    To maintain the structural integrity of graphite components during plant operation a visual inspection using a TV camera as an in-service inspection is planned in the High Temperature Engineering Test Reactor. In order to verify the in-service inspection method a preliminary analytical and experimental studies were performed. In the analytical study the harmful flaw size was determined from a viewpoint of structural integrity based on the fracture mechanics approach. Furthermore, the visible flaw size was determined by the TV camera performance test with graphite test specimens having several kinds of artificial flaws. This paper presents the analytical result on the harmful flaw size and the experimental result on the visible flaw size. From both results the applicability on the visual inspection by the TV camera as the in-service inspection is discussed in this paper. (author)

  2. Benediktinské opatství sv. Petra a Pavla ve Vilémově. Příspěvek k historii a stavební podobě "zapomenutého" kláštera pod Železnými horami

    Czech Academy of Sciences Publication Activity Database

    Kovář, M.; Musílek, Martin

    2009-01-01

    Roč. 117, č. 3 (2009), s. 157-183 ISSN 1803-1382 Grant - others:AV ČR(CZ) M300090903 Institutional research plan: CEZ:AV0Z90090514 Keywords : Bohemia * Middle Ages * Vilémov * monastery of Vilémov * Benedictine * Benedictine abbey Subject RIV: AA - Philosophy ; Religion

  3. Safety Evaluation Report, pump and valve inservice testing program, Yankee Rowe Nuclear Power Station (Docket No. 50-29). Revision 1

    International Nuclear Information System (INIS)

    Ransom, C.B.; Rockhold, H.C.

    1985-10-01

    The staff reviewed the Yankee Rowe IST program submittal dated October 2, 1981 and evaluated the proposed tests for compliance with the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, 1977 Edition, through the Summer of 1978 Addenda. Those items not in compliance were discussed in a working session with Yankee Atomic Electric Company personnel, USNRC representatives, and EG and G Idaho reviewers on June 22, 1982. The evaluations presented in this SER of the Yankee Rowe pump and valve inservice testing program and the associated relief requests are those of the NRC staff. These findings apply only to component testing

  4. Assessing the In-Service Needs of Basic School Natural Science ...

    African Journals Online (AJOL)

    ... that no significant associations existed. It was recommended among other things that in-service training courses be used as platforms in upgrading the teachers' knowledge and skills. Additionally, in-service course organizers should first assess the in-service needs of participants before providing the appropriate support ...

  5. A study on the optimization of test interval for check valves of Ulchin Unit 3 using the risk-informed in-service testing approach

    International Nuclear Information System (INIS)

    Kang, D. I.; Kim, K. Y.; Yang, Z. A.; Ha, J. J.

    2002-01-01

    We optimized the test interval for check valves of Ulchin Unit 3 using the risk-informed in-service testing (IST) approach. First, we categorized the IST check valves for Ulchin Unit 3 according to their contributions to the safety of Ulchin Unit 3. Next, we performed the risk analysis on the relaxation of test interval for check valves identified as relatively low important to the safety of Ulchin Unit 3 to identify the maximum increasable test interval of them. Finally, we estimated the number of tests of IST check valves to be performed due to the changes of test interval. These study results are as follows: The categorization of IST check valve importance; the number of the HSSCs is 24(11.48%), the ISSCs is 40 (19.14%), and the LSSCs is 462(69.38%). The maximum increasable test interval; 6 times of current test interval of ISSCs2 and 40 times of that of LSSCs. The number of tests of IST check valves to be performed during 6 refueling time can be reduced from 7692 to 1333 ( 82.7%)

  6. Gender Diversity and ICT Literacy among Nigerian In-Service ...

    African Journals Online (AJOL)

    The instrument used for this study was the self-designed ICT Literacy Scale (ILS) with a coefficient of 0.91. Mean and Standard Deviation, t-test, Pearson Product Moment Correlation Coefficient were utilized for the data analysis. The findings revealed that there gender is a determining factor of in-service teachers' overall ...

  7. In-service education and training as experienced by registered nurses.

    Science.gov (United States)

    Norushe, T F; Van Rooyen, D; Strumpher, J

    2004-11-01

    Nursing is a dynamic profession that is subject to rapid changes in health care provision, hence the need for in-service training programmes for nurses. Newly employed registered nurses require in-service training in order to update them regarding the latest developments in nursing practice. The researcher noted that some newly appointed registered nurses were not competent in all aspects relating to their tasks. This could have been due to a knowledge deficit relating to either new developments or of the procedure relating to a specific task. In some institutions newly-appointed registered nurses on probation reported not receiving in-service training for six months or longer, yet they were still expected to perform their tasks efficiently. The objectives of the study were to, firstly, explore and describe the experiences of registered nurses regarding in-service training programmes in their institutions and, secondly, to make recommendations to Nursing Service Managers relating to the development of effective in-service training programmes in their institutions. A qualitative, exploratory, descriptive design was implemented. Data was analysed using Tesch's descriptive approach (in Creswell, 1994:155). Two main themes emerged, namely that registered nurses experienced in-service training programmes as inadequate and reacted negatively towards them. This article focuses on the experiences of registered nurses relating to in-service training programmes, as well as the formulation of guidelines to assist nursing service managers in the development of effective in-service training programmes.

  8. Ultrasonic in-service testing of pressure vessel bodies of nuclear power reactors

    International Nuclear Information System (INIS)

    Obraz, J.

    1978-01-01

    In-service ultrasonic testing of reactor pressure vessels is described using a system of probes for simultaneous testing of material or weld joint thicknesses. The signal is transmitted from a common output via a 30 m long cable to electronic evaluation equipment. The methods are described of ultrasonic detection of fatigue cracks. The static calculation of the dependence of echo amplitudes on crack orientation and the dynamic calculation of the crack orientation effect are described for the indirect reflection technique. In testing, angular probes with gap-type acoustic coupling operating at a frequency of 2 MHz were preferably used. For detecting planar defects of more than 10 mm in size inclined by more than +-10deg probes operating at a frequency of 1 MHz were more advantageous. The direct reflection technique is suitable for detecting defects near the surface (10 to 20 mm) and for cases when the indirect reflection technique cannot be used. For this technique a focusing probe operating at a frequency of 2 MHz is suitable. The strong dependence of the echo amplitude on the crack depth is a disadvantage of the technique. Defects near the surface, i.e., immediately under cladding are best detected by means of a double probe transmitting transversal waves at an angle of 60deg. Experimental measurements were carried out on materials with artificial defects of the type of bores with flat bottom. (J.P.)

  9. Characterization by notched and precracked Charpy tests of the in-service degradation of RPV steel fracture toughness

    Energy Technology Data Exchange (ETDEWEB)

    Fabry, A.

    1997-01-01

    The current engineering and regulatory practice to estimate fracture toughness safety margins for nuclear reactor pressure vessels (RPVs) relies heavily on the CVN impact test. Techniques to estimate in-service toughness degradation directly using a variety of precracked specimens are under development worldwide. Emphasis is on their miniaturization. In the nuclear context, it is essential to address many issues such as representativity of the surveillance programs with respect to the vessel in terms of materials and environment, transferability of test results to the structure (constraint and size effects), lower bound toughness certification, creadibility relative to trends of exising databases. An enhanced RPV surveillance strategy in under development in Belgium. It combines state-of-the-art micromechanical and damage modelling to the evaluation of CVN load-deflection signals, tensile stress-strain curves and slow-bend tests of reconstituted precracked Charpy specimens. A probabilistic micromechanical model has been established for static and dynamic transgranular cleavage initiation fracture toughness in the ductile-brittle transition temperature range. This model allows to project toughness bounds for any steel embrittlement condition from the corresponding CVN and static tensile properties, using a single scaling factor defined by imposing agreement with toughness tests in a single condition. The outstanding finding incorporated by this toughness transfer model is that the microcleavage fracture stress is affected by temperature in the ductile-brittle transition and that this influence is strongly correlated to the flow stress: this explains the shape of the K{sub Ic}n K{sub Id} temperature curves as well as the actual magnitude of the strain rate and irradiation effects. Furthermore, CVN crack arrest loads and fracture appearance are also taken advantage of in order to estimate K{sub Ia} degradation. Finally, the CVN-tensile load-temperature diagram

  10. Motor operated valve testing and the 'rate of loading' phenomenon

    International Nuclear Information System (INIS)

    Black, B.R.

    1991-01-01

    This paper discusses valve design features which affect the ability to predict motor operated valve (MOV) performance and reviews factors which should be considered when selecting switch settings to limit stem loads. Considerable attention is given to the rate of loading phenomenon which affects the relationship between valve stem thrust and actuator spring pack deflection. Equations are developed, and testing is discussed which permit the construction of an MOV dynamic model. Factors which must be considered when maintaining switch settings correct throughout the life of the plant are discussed. And switch setting acceptance criteria for use with baseline Static and Design Basis testing are suggested

  11. The Information-Seeking Habits of In-Service Educators

    Science.gov (United States)

    Shipman, Todd; Bannon, Susan H.; Nunes-Bufford, Kimberly

    2015-01-01

    Research on information literacy and educators has focused on preservice educators and learning information literacy skills. Little research exists on in-service educators and their information literacy skills. Purposes of this study were to identify information sources that in-service educators used; to determine relationships between information…

  12. Inservice Teacher Education in Nigeria: A Case Study.

    Science.gov (United States)

    Esu, Akon E. O.

    1991-01-01

    Examines the current status of in-service teacher education in Nigeria, indicating three approaches: the central office approach; the long vacation program; and the Associateship Certificate in Education distance learning approach. Recommendations for planning and implementing in-service teacher education programs in Nigeria are noted. (SM)

  13. Results of the motor-operated valve engineering and testing program

    International Nuclear Information System (INIS)

    Black, B.R.

    1994-01-01

    The Texas Utilities Electric Company (TU Electric) motor-operated valve (MOV) program for implementing the recommendations of Generic Letter 89-10 has typically included the following: refurbishing each actuator, verifying each actuator's as-built configuration, testing each actuator's motor on a dynamometer, testing each actuator's torque spring pack (which is used to control the torque developed), testing each fully refurbished and reassembled actuator on a torque test stand, and testing as many MOVs as practicable both without fluid flow through the valve and with the maximum test conditions reasonably achievable (static and differential pressures (DP) conditions, respectively). Test data are acquired at 1,000 samples per second for stem thrust, stem torque, stem position, actuator compensator spring pack deflection, actuator torque spring pack deflection, motor current, motor voltage, motor three-phase power, valve upstream pressure, and valve downstream pressure, wherever practicable

  14. Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This guide covers the general procedures to be considered for conducting an in-service thermal anneal of a light-water moderated nuclear reactor vessel and demonstrating the effectiveness of the procedure. The purpose of this in-service annealing (heat treatment) is to improve the mechanical properties, especially fracture toughness, of the reactor vessel materials previously degraded by neutron embrittlement. The improvement in mechanical properties generally is assessed using Charpy V-notch impact test results, or alternatively, fracture toughness test results or inferred toughness property changes from tensile, hardness, indentation, or other miniature specimen testing (1). 1.2 This guide is designed to accommodate the variable response of reactor-vessel materials in post-irradiation annealing at various temperatures and different time periods. Certain inherent limiting factors must be considered in developing an annealing procedure. These factors include system-design limitations; physical constrain...

  15. Time-independent and time-dependent contributions to the unavailability of standby safety system components

    International Nuclear Information System (INIS)

    Lofgren, E.V.; Uryasev, S.; Samanta, P.

    1997-01-01

    The unavailability of standby safety system components due to failures in nuclear power plants is considered to involve a time-independent and a time-dependent part. The former relates to the component's unavailability from demand stresses due to usage, and the latter represents the component's unavailability due to standby-time stresses related to the environment. In this paper, data from the nuclear plant reliability data system (NPRDS) were used to partition the component's unavailability into the contributions from standby-time stress (i.e., due to environmental factors) and demand stress (i.e., due to usage). Analyses are presented of motor-operated valves (MOVs), motor-driven pumps (MDPs), and turbine-driven pumps (TDPs). MOVs fail predominantly (approx. 78 %) from environmental factors (standby-time stress failures). MDPs fail slightly more frequently from demand stresses (approx. 63 %) than standby-time stresses, while TDPs fail predominantly from standby-time stresses (approx. 78 %). Such partitions of component unavailability have many uses in risk-informed and performance-based regulation relating to modifications to Technical Specification, in-service testing, precise determination of dominant accident sequences, and implementation of maintenance rules

  16. A Comparison of Two Approaches to Developing In-Service Teachers' Knowledge and Strategies for Teaching Nature of Science

    Science.gov (United States)

    Vhurumuku, Elaosi; Chikochi, Andrew

    2017-01-01

    This paper reports the results of a study that compared two approaches to developing in-service teachers' subject matter knowledge and strategies for teaching nature of science. A treatment post-test only quasi-experimental research design was used. One group of in-service teachers (n = 15) was taught using what is called a capsular approach. In…

  17. Application of non-destructive testing and in-service inspection to research reactors. Results of a co-ordinated research project

    International Nuclear Information System (INIS)

    2001-12-01

    -destructive testing (NDT), are generally called in-service inspections (ISI) and, together with the above specific techniques, are the subject of the present TECDOC. The main objectives of the TECDOC are to present a number of these special techniques and to give guidance for their application. The guidance and recommendations given in this publication form the basis for the conduct of ISI of research reactors with limited hazard potential to the public. This TECDOC is based on the results of a Co-ordinated Research Project (CRP) on the Application of Non-destructive Testing and In-service Inspection to Research Reactors that the IAEA organized in 1995 to supplement its activities on research reactor ageing within its Research Reactor Safety Programme (RRSP). Because of the importance of such in-service inspections within the programmes for the management of ageing in research reactors, this TECDOC will be useful to a large fraction of the currently operating research reactors that are over 30 years old

  18. Technology Integration Support Levels for In-Service Teachers

    Science.gov (United States)

    Williams, Mable Evans

    2017-01-01

    In-service teachers across the globe are expected to integrate technology in their respective instructional content area. The purpose of this qualitative study was to explore the perceptions of in-service teachers concerning building-level support for technology integration. Participants in the study were asked to participate in semi-structured…

  19. Dvoutrámový most přes řeku Bebravu

    OpenAIRE

    Hlavoň, Michal

    2017-01-01

    Předmětem diplomové práce je návrh mostu přes řeku Bebrava. Hlavní náplní je výpočet spojité nosní konstrukce o třech polích. Byly zpracovány tři varianty, z nichž byla zvolena varianta předpjatého dvoutrámovéhomostu.Rozpětí jednotlivých polích je 23+29+23 m. Statický model a účinky zatížení jsou řešeny v programu SciaEngeneer 15.1. Všechny výpočty jsou provedeny dle Eurokódů. The subject of diploma thesis is the design of the grinder over river Bebrava. The maintopic is static calculation...

  20. In-Service Teacher Education: Some Suggestions for Improvement ...

    African Journals Online (AJOL)

    This paper therefore examines teacher education, especially in-service teacher education and how it has been practised elsewhere. It is hoped that education policy makers will take note of some of the issues raised in this paper as the one day workshop which has hitherto been the most used strategy of in-service teacher ...

  1. 49 CFR 214.529 - In-service failure of primary braking system.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false In-service failure of primary braking system. 214... Maintenance Machines and Hi-Rail Vehicles § 214.529 In-service failure of primary braking system. (a) In the event of a total in-service failure of its primary braking system, an on-track roadway maintenance...

  2. Software life after in-service

    International Nuclear Information System (INIS)

    Tseng, M.; Eng, P.

    1993-01-01

    Software engineers and designers tend to conclude a software project at the in-service milestone of the software life cycle. But the reality is that the 'life after in-service' is significantly longer than other phases of the life cycle, typically 20 years or more depending on the maintainability of the hardware platform and the designed life of the plant. During this period, the software asset (as with other physical assets in the plant) continues to be upgraded to correct deficiencies, meet new requirements, cope with obsolescence of equipment and so on. The software life cycle ends with a migration of the software to a different platform. It is typical in a software development project to put a great deal of emphasis on design methodologies, techniques, tools, development environment, standard procedures, and project management to ensure quality product is delivered on schedule and within budget. More often than not, a disproportion of emphasis is placed on the issues and needs of the in-service phase. Once the software is in-service, the designers move on to other projects, while the maintenance and support staff must manage the software. This paper examines the issues in three steps. First it presents a view of software from maintenance and support staff perspectives, including complexity of software, suitability of documentation, configuration management, training, difficulties and risks associated with making changes, required skills and knowledge. Second, it identifies the concerns raised from these viewpoints, including costs of maintaining the software, ability to meet additional requirements, availability of support tools, length of time required to engineer and install changes, and a strategy for the migration of software asset. Finally it discusses some approaches to deal with the concerns. (Author) 5 refs., fig

  3. RITES: Online (Reaching In-service Teachers with Earth Sciences Online)

    Science.gov (United States)

    Baptiste, H.

    2003-12-01

    The RITES: Online project team (Drs. H. Prentice Baptiste, Susan Brown, Jennifer Villa) believed that the power of technology could not be effectively utilized unless it was grounded in new models of teaching and learning based on a student centered and project based curriculum, that increased opportunities for active, hands-on learning and respect for multiculturalism. We subscribe to an inquiry approach to learning. Specifically, science teaching should actively engage the learners in activities that draw on multiple abilities and learning styles. Recent brain-based research has shown that human beings construct knowledge through actions and interactions within their environment. Learning occurs in communities, and new ideas are linked to previous knowledge and constructed by the learner. Knowledge is acquired by making connections. We believed the aforementioned ideas and points to be equally true for the teacher candidates and inservice teachers participating in the RITES: Online project as well as for their students. The ESSEA science courses were delivered by distance learning via the university WebCt distance education system to teacher candidates (preservice teachers) and inservice teachers. Teacher candidates and inservice teachers were encouraged to use technology when involving their students in science inquiry activities and to record their students' involvement in science activities with digital cameras. Teacher candidates and inservice teachers involve in the ESSEA courses are engaged in earth science inquiry activities relevant to the four spheres (atmosphere, lithosphere, biosphere, hydrosphere) with the students in their classes. This presentation will highlight teacher candidates and inservice teachers in the roles of designer, researcher, and collaborator. Examples of student works will also be a part of the Power point presentation. As a result of our courses our teachers have attained the following positive outcomes: 1) Teacher candidates and

  4. Automated ultrasonic testing of nuclear reactor welds and overlays in pre-service and in-service inspections

    International Nuclear Information System (INIS)

    Sladky, J.

    1988-01-01

    Since 1982, automatic pre-service and in-service checks are being made of welded joints and overlays on pressure vessels of WWER-440 nuclear reactors in Czechoslovakia. This is being done using the SKODA REACTORTEST TRC facility which is used for checking peripheral welded joints on the pressure vessel, neck joints, overlays in other selected areas of the cylindrical section of the pressure vessel, on radius transitions of the pressure vessel and of necks, and on the cylindrical part of necks, and also for checking the base material in selected parts of the pressure vessel and the base material of the neck extension piece. The tests are of two types, namely tests of peripheral welds and overlays of the cylindrical parts of the pressure vessel, and tests of the necks. Different ultrasonic probe holders are used for the tests, with totally different design. Ultrasonic probes which were initially used were of foreign make while at present, those of Czechoslovak make are used. For each pressure vessel a set of ultrasonic probes is used which should suffice for the life of the vessel. Experience gained so far is being used in work on the project of a new device for testing nuclear reactor presure vessels from the inside. (Z.M.)

  5. In-Service Science Teachers' Attitude towards Information Communication Technology

    Science.gov (United States)

    Kibirige, I.

    2011-01-01

    The purpose of this study is to determine the attitude of in-service science teachers towards information communication technology (ICT) in education. The study explores the relationship between in-service teachers and four independent variables: their attitudes toward computers; their cultural perception of computers; their perceived computer…

  6. X-ray tomographic in-service testing of girth welds - The European project TomoWELD

    International Nuclear Information System (INIS)

    Ewert, Uwe; Redmer, Bernhard; Walter, David; Thiessenhusen, Kai-Uwe; Bellon, Carsten; Nicholson, P. Ian; Clarke, Alan; Finke-Haerkoenen, Klaus-Peter; Scharfschwerdt, Joerg W.; Rohde, Karsten

    2015-01-01

    The new standard ISO 17636-2: 2013 'NDT of welded joints - Radiographic testing - Part 2: X- and gamma radiographic testing with digital detectors ''defines the testing practice for digital radiography of welds for the production and in-service inspection. Furthermore the DIN 25435-7:2014 ''In-service inspections of the components of the primary circuit of light water reactors - Part 7: Radiographic testing'' was published. The essential requirements are discussed. The new TomoWELD system can both perform measurements according to these standards as well as record tomographic cross-sectional images (equivalent to metallographic sections), to determine image sizes. Areas of application are chemical and nuclear facilities. It provides a fast testing of girth welds as compared to the use of film or imaging plates. In 2006 the mechanized planar tomography system, TomoCAR, was already introduced, with one could measure cross-sectional images. TomoWELD uses a new photon counting and energy resolving detector with CdTe-CMOS crystal hybrids. The new detector allows the choice of energy thresholds, and enables the reduction of the influence of scattered radiation on the radiographic images and the reconstructed cross-sectional images. An optimized irradiation geometry with a new manipulator design and a fast GPU-based reconstruction algorithm can be used to accelerate the reconstruction and to improve the reconstruction results. The size and the shape of planar and voluminous irregularities can be determined. The concept and the first pictures will be presented. (Contains mainly PowerPoint slides). [de

  7. Long-term performance of motor-operated valves

    Energy Technology Data Exchange (ETDEWEB)

    Scarbrough, T.G.

    1996-12-01

    The U.S. Nuclear Regulatory Commission (NRC) requires that motor-operated valves (MOVs) important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Despite these requirements, operating experience and research revealed problems with the performance of MOVs in operating nuclear power plants. In response to the concerns about MOV performance, the NRC issued Generic Letter (GL) 89-10, {open_quotes}Safety-Related Motor-Operated Valve Testing and Surveillance,{close_quotes} and its supplements. Most licensees have completed the aspects of their GL 89-10 programs associated with the review of MOV design bases, verification of MOV switch settings initially, testing of MOVs under design-basis conditions where practicable, and improvement of evaluations of MOV failures and necessary corrective action. Licensees are establishing processes to ensure that the long-term aspects of their MOV programs, such as periodic verification of MOV capability and the trending of MOV problems, are maintained. The NRC staff is developing a generic letter to address periodic verification of MOV design-basis capability.

  8. Long-term performance of motor-operated valves

    International Nuclear Information System (INIS)

    Scarbrough, T.G.

    1996-01-01

    The U.S. Nuclear Regulatory Commission (NRC) requires that motor-operated valves (MOVs) important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Despite these requirements, operating experience and research revealed problems with the performance of MOVs in operating nuclear power plants. In response to the concerns about MOV performance, the NRC issued Generic Letter (GL) 89-10, open-quotes Safety-Related Motor-Operated Valve Testing and Surveillance,close quotes and its supplements. Most licensees have completed the aspects of their GL 89-10 programs associated with the review of MOV design bases, verification of MOV switch settings initially, testing of MOVs under design-basis conditions where practicable, and improvement of evaluations of MOV failures and necessary corrective action. Licensees are establishing processes to ensure that the long-term aspects of their MOV programs, such as periodic verification of MOV capability and the trending of MOV problems, are maintained. The NRC staff is developing a generic letter to address periodic verification of MOV design-basis capability

  9. Institutional Roles for In-Service Education of School Administrators.

    Science.gov (United States)

    Lynch, Patrick D., Ed.; Blackstone, Peggy L., Ed.

    This document is a compilation of papers read at a 4-day conference attended by 60 participants from throughout the United States. Chapters include (1) "In-Service Education of School Administrators: Background, Present Status, and Problems," by Robert B. Howsam; (2) "Notes on Institutional Relationships in the In-Service Education of the…

  10. Factors affecting the nurses’ motivation for participating in the in-service training courses: A case study

    Directory of Open Access Journals (Sweden)

    Zahra Sajjadnia

    2015-11-01

    Full Text Available Introduction: Due to the vital role of nurses and the effects of scientific advances on nursing care, providing high quality nursing services is not possible without participating in the in-service training programs and becoming familiar with the new techniques. This study aimed to determine the motivational factors influencing the participation in the in-service training courses among nurses working in the teaching hospitals affiliated to Shiraz University of Medical Sciences in 2013. Method: This was an applied, cross-sectional and descriptive-analytical study. A sample of 216 nurses working in the teaching hospitals affiliated to Shiraz University of Medical Sciences was selected using stratified sampling proportional to size and simple random sampling methods. The required data were collected using a questionnaire determining the motivational factors influencing the nurses’ participation in the in-service training courses, including personal factors, organizational factors, and those related to the profession and the training courses planning. SPSS 18.0 and some statistical tests including ANOVA, Independent-Samples T-Test, as well as Pearson Correlation Coefficient were used to analyze the collected data. Results: The results showed that the mean score of nurses’ motivation for participating in the in-service training programs was 3.41±0.5. Also, the highest and lowest means of motivational factors affecting the studied nurses’ participation in the in-service courses were associated with the factors related to the profession (3.75 ± 0.71, and those related to the training courses planning (3.20 ± 0.59, respectively. In addition, there were significant associations between the personal factors (p=0.037 and factors related to the profession (p=0.047 and the studied nurses’ positions, between the organizational factors and their employment status (p=0.007, and between the factors related to the training courses planning and the

  11. A Leadership Model for University Geology Department Teacher Inservice Programs.

    Science.gov (United States)

    Sheldon, Daniel S.; And Others

    1983-01-01

    Provides geology departments and science educators with a leadership model for developing earth science inservice programs. Model emphasizes cooperation/coordination among departments, science educators, and curriculum specialists at local/intermediate/state levels. Includes rationale for inservice programs and geology department involvement in…

  12. Scheduling and coordination for in-service inspection of nuclear power plant

    International Nuclear Information System (INIS)

    Li Songbai

    1996-11-01

    Based on the practice and experiences of pre-service and in-service inspections for Daya Bay Nuclear Power Plant (NPP) by Research Institute of Nuclear Power Operation (RINPO) following RSEM code, requirements of utility and actual situation in China, the in-service inspection preparation for organization, techniques and equipment/tooling, materials, personnel and documentation is briefly described. And the scheduling and coordinating consideration for planed in-service inspection activities during NPP outage is emphatically introduced. (2 refs., 4 figs.)

  13. Evaluation of structural welds with respect to reliability and inservice inspection

    International Nuclear Information System (INIS)

    Marci, G.

    1980-01-01

    The ongoing developments with respect to large forgings for nuclear pressure vessels and the present philosophy of inservice inspection in the Federal Republic of Germany (FRG) (inspection of weld regions only) seem to be oriented towards a monolithic pressure vessel requiring no inservice inspection. This raises questions as to the task of inservice inspection in the framework of the total reliability of a nuclear pressure vessel. The inherent 'weak spots' associated with welds of ferritic low alloyed steels are the microstructural features of stress relief cracks and regions of coarse grains. An analysis as to the effects of stress relief cracks and regions of coarse grains in the heat affected zones of welds on subcritical crack growth is performed. It is shown that these 'weak spots' cannot be considered a particular safety hazard to vessel integrity. Therefore welds per se should not constitute the criteria for the performance of inservice inspection. Rather, the inservice inspection programme should check the regions where manufacturing history, loading conditions, and materials degradation are expected to enhance subcritical crack growth. (author)

  14. The association between in-service sexual harassment and post-traumatic stress disorder among Department of Veterans Affairs disability applicants.

    Science.gov (United States)

    Murdoch, Maureen; Polusny, Melissa A; Hodges, James; Cowper, Diane

    2006-02-01

    The goal was to describe the association between post-traumatic stress disorder (PTSD) and in-service sexual harassment in a nationally representative sample of Department of Veterans Affairs PTSD disability applicants. The study was a cross-sectional survey. Of 4,918 eligible veterans, 3,337 (68%) returned surveys. Nonresponse bias appeared to be minimal. After adjustment for other reported traumas, women's reported in-service sexual harassment severity was significantly associated with PTSD symptom severity (p men and for in-service sexual assault among the women. Men showed no association between in-service sexual harassment and PTSD (p = 0.33), although power was low for this test. Sexual harassment significantly contributed to female veterans' PTSD symptoms; its contribution to men's symptoms was unclear. We discuss mechanisms through which sexual harassment might affect PTSD symptom severity, including the possibility that sexual harassment sometimes meets the Diagnostic and Statistical Manual of Mental Disorders, Fourth Edition, definition of a criterion A stressor.

  15. Application of non-destructive testing and in-service inspections to research reactors and preparation of ISI programme and manual for WWR-C research reactors

    International Nuclear Information System (INIS)

    Khattab, M.

    1996-01-01

    The present report gives a review on the results of application of non-destructive testing and in-service inspections to WWR-C reactors in different countries. The major problems related to reactor safety and the procedure of inspection techniques are investigated to collect the experience gained from this type of reactors. Exchangeable experience in solving common problems in similar reactors play an important role in the effectiveness of their rehabilitation programmes. 9 figs., 4 tabs

  16. New developments in containment in-service inspection requirements

    International Nuclear Information System (INIS)

    Staffiera, J.E.

    1995-01-01

    Section 11 of the ASME Boiler and Pressure Vessel Code contains requirements for inservice inspection of nuclear power plant components. Development of ASME Code requirements for containment inservice inspection was begun in 1977, and in 1979 the first such requirements were published in the form of Code Case N-236. Formal inclusion of these requirements in Section 11 of the ASME Code occurred with publication of Subsection IWE, ''Rules for inservice Inspection of Class MC Components of Nuclear Power Plants,'' in the 1980 Edition, Winter 1981 Addenda. At that time, inspection emphasis on nuclear power construction and operation activities was placed on welds and welding processes associated with steel containments and metallic liners of concrete containments. The need for repair-welding requirements was necessitated by containment design modifications for conditions not considered in several original plant designs. Welds in steel containments and metallic liners of concrete containments have not required significant amounts of repair, however, degradation of base metal in containments has become a major concern. Various degradation mechanisms have been identified as potential causes of damage to containment surfaces, including fatigue, corrosion and material embrittlement due to long-term radiation exposure. As a result of these concerns, and in response to comments generated by the Committee to Review Generic Requirements (CRGR) of the NRC in its review of Subsection IWE, emphasis on weld-based inservice inspection was redirected toward a containment-surface inservice inspection program. Significant changes were made to accommodate this re-emphasis. The majority of these changes were published in the 1992 Edition, with the 1992 Addenda, of Subsection IWE. The NRC Proposed Rulemaking was issued for a 75-day public comment period in January, 1994. This period was extended at the request of nuclear industry organizations to allow for meaningful evaluation

  17. Experience with the WWER-440 MW reactor pressure vessel in-service inspections and evaluation of their results

    International Nuclear Information System (INIS)

    Brumovsky, M.; Kralovec, J.; Prepechal, J.; Sulc, J.

    1989-01-01

    The Power Machinery Plant of Skoda Works in Plzen carries out in-service inspections of WWER-440 MW reactor pressure vessels by means of remote controlled inspection equipment - the TRC reactor test system, and some other inspections devices. The results of the in-service inspections were evaluated by methods based on the fracture mechanics approach, the knowledge of stress and strain distribution, and the operating history of the pressure vessels. Examples of types of defects found and their analysis are shown. (author). 1 tab

  18. Kinetics and tissue distribution of the radiolabeled chimeric monoclonal antibody MOv18 IgG and F(ab')2 fragments in ovarian carcinoma patients

    NARCIS (Netherlands)

    Buist, M. R.; Kenemans, P.; den Hollander, W.; Vermorken, J. B.; Molthoff, C. J.; Burger, C. W.; Helmerhorst, T. J.; Baak, J. P.; Roos, J. C.

    1993-01-01

    Twenty-four patients suspected of having ovarian carcinoma received i.v. injection with a combination of radiolabeled intact IgG (1 mg) and F(ab')2 fragments (1 mg) of the chimeric monoclonal antibody MOv18, each form labeled with 1.85 MBq 131I or 125I. Laparotomy was performed either 2 or 6 days

  19. In-service inspection of pressurized water reactors

    International Nuclear Information System (INIS)

    Rapin, M.; Saglio, R.

    1983-01-01

    French legislation, which is more demanding than in other countries, had led Electricite de France, the State-owned utility, to acquire better performance in-service inspection facilities than those which existed previously. This fact has spurred the industrial development of the new technical facilities which are used worldwide today. This article presents the ''in-service inspection machine'' (MIS) for the inspection of the welds of a PWR vessel, and the inspection device of steam generator tubes; the MIS allow a remote-viewing, ultrasonic and gamma-graphic inspection; Foucault currents are the only one method adapted to the inspection steam generator tubes [fr

  20. Development of quantitative evaluation procedure of in-service materials degradation

    International Nuclear Information System (INIS)

    Takahashi, Hideaki

    1992-01-01

    The quantitative nondestructive evaluation procedure for detecting in-service materials degradation of low alloy structural steels by both small punch test and the electrochemical method has been developed. The static and dynamic small punch test method have been developed in order to apply this technique to R and D study for fusion reactor material development, such as 14 MeV irradiation damage evaluation. The characteristic changes in polarization curves attributed to IGC have an excellent correlation with shifts in FATT caused by temper embrittlement for Cr-Mo and Cr-Mo-V steels. (author)

  1. Pre- and In-Service Preschool Teachers' Science Teaching Efficacy Beliefs

    Science.gov (United States)

    Aslan, Durmus; Tas, Isil; Ogul, Irem Gürgah

    2016-01-01

    In this study, pre- and in-service preschool teachers' science teaching efficacy beliefs were investigated. The sample included 100 pre-service (50 first grades and 50 last grades) and 73 in-service preschool teachers. As a data collection tool "Science Teaching Efficacy Belief Instrument" was used. Findings indicated that in-service…

  2. Pre- and in-Service Teachers Reading and Discussing Informational Texts

    Directory of Open Access Journals (Sweden)

    Theresa A. Deeney

    2016-05-01

    Full Text Available This study investigates U.S. elementary (kindergarten-Grade 6, ages 5-12 pre- and in-service teachers’ discussions of informational texts to understand current practices and identify needs with respect to how teachers support students in building knowledge from complex informational text as specified in the grade-level expectations of the Common Core State Standards adopted in many U.S. states. Transcripts and reflections from 17 in-service and 31 pre-service teachers’ informational text discussions were analyzed for teachers’ focus on the text, background knowledge, and text/background knowledge. In addition, transcripts were analyzed for the types of text ideas teachers targeted (details/main ideas, the comprehension demands placed on students, how teachers used follow-up moves to encourage higher level thinking, and how teachers use transcripts of their discussions to analyze and critique their own practice. Findings suggest that both pre- and in-service teachers draw heavily on students’ background knowledge and text details in their questioning; but differences exist in how pre- and in-service teachers use follow-up responses to promote knowledge building. Findings also suggest that both pre- and in-service teachers can use their transcripts to recognize areas of need, and offer themselves suggestions to better support students’ understanding. Implications are offered for teacher education and professional development.

  3. Inservice Inspection in the Fugen

    OpenAIRE

    1983-01-01

    Pressure tube type reactors have specific components orstructures,compared with light water reactors.They are(1) steam drums(2) reactor inlet headers(3) reactor inlet and outlet pipies(4) pressure tubes.Much attention is paid upon Inservice Inspection (ISI)of the above components.

  4. Development of Heat-Affected Zone Hardness Limits for In-Service Welding

    Science.gov (United States)

    2009-09-29

    Welding onto in-service pipelines is frequently required to facilitate a repair or to install a branch connection using the "hot tapping" technique. Welds made in-service cool at an accelerated rate as the result of the ability of the flowing content...

  5. Individualized In-Service Teacher Education. (Project IN-STEP). Evaluation Report, Phase II.

    Science.gov (United States)

    Thurber, John C.

    Phase 2 of Project IN-STEP was conducted to revise, refine, and conduct further field testing of a new inservice teacher education model. The method developed (in Phase 1--see ED 003 905 for report) is an individualized, multi-media approach. Revision activities, based on feedback provided for Phase 1, include the remaking of six videotape…

  6. An Examination of Technology Training Experiences from Teacher Candidacy to In-Service Professional Development

    Science.gov (United States)

    Williams, Mable Evans

    2017-01-01

    The purpose of this qualitative study was to explore the perceptions of in-service teachers concerning the effectiveness of technology training from a teacher education preparation program to in-service professional development. The findings of the study revealed that inservice teachers have had varying degrees of technology experiences from their…

  7. Issues and Challenges of Providing Online Inservice Teacher Training: Korea's experience

    Directory of Open Access Journals (Sweden)

    Insung Jung

    2001-07-01

    Full Text Available To meet the need for flexible and interactive teacher training, the Korean government created a Cyber Teacher Training Center (CTTC in the summer of 1997. The CTTC project developed a software platform for managing online inservice teacher training, 11 general training courses, with plans to add more courses each year. This article examines the needs met through the introduction of online inservice teacher training and the strategies that have been employed in the process. This paper also analyzes the major impacts of online teacher training and looks at the challenges facing online inservice teacher training in the coming years.

  8. Rail vehicle dynamic response to a nonlinear physical 'in-service' model of its secondary suspension hydraulic dampers

    Science.gov (United States)

    Wang, W. L.; Zhou, Z. R.; Yu, D. S.; Qin, Q. H.; Iwnicki, S.

    2017-10-01

    A full nonlinear physical 'in-service' model was built for a rail vehicle secondary suspension hydraulic damper with shim-pack-type valves. In the modelling process, a shim pack deflection theory with an equivalent-pressure correction factor was proposed, and a Finite Element Analysis (FEA) approach was applied. Bench test results validated the damper model over its full velocity range and thus also proved that the proposed shim pack deflection theory and the FEA-based parameter identification approach are effective. The validated full damper model was subsequently incorporated into a detailed vehicle dynamics simulation to study how its key in-service parameter variations influence the secondary-suspension-related vehicle system dynamics. The obtained nonlinear physical in-service damper model and the vehicle dynamic response characteristics in this study could be used in the product design optimization and nonlinear optimal specifications of high-speed rail hydraulic dampers.

  9. Research of nuclear power plant in-service maintenance based on virtual reality

    International Nuclear Information System (INIS)

    Wang Yong; Kuang Weijun

    2015-01-01

    This paper presents a method of constructing nuclear power plant in-service maintenance virtual simulation scene and virtual maintenance process. Taking air baffles dismantling process of CAP1400(China Advanced Passive 1400) nuclear power plant as an instance, this paper discusses ergonomics, space analysis, time assessment based on virtual reality in the process of in-service maintenance. It demonstrates the advantage of using VR technology to design and verify in-service maintenance process of nuclear power plant compared to the conventional way. (author)

  10. The ASME research task force on risk-based in-service inspection

    International Nuclear Information System (INIS)

    Balkey, K.R.; Chapman, O.J.V.

    1997-01-01

    The use of risk-based methods in the development of in-service inspection (ISI) and in-service testing (IST) programs for nuclear power plant and other industrial applications has been studied for the last several years through the American Society of Mechanical Engineers Centre for Research and Technology Development (ASME 1991, 1992, 1994, 1996). The results of this work are being used as a foundation to develop specific requirements for implementation of risk-based technology in ASME Codes and Standards, regulatory requirements and industry programs both in the U.S. and other countries. This paper provides a brief overview of the ASME Research Methodology and how it has been adapted for application to the inspection of piping within the USA. It also relates how the reliability of nondestructive examination (NDE) methods for pressure boundary components can impact the risk and discusses the relationship between this and NDE qualification/demonstration now being implemented in Europe and the USA. (orig.)

  11. On-line monitoring and inservice inspection in codes

    International Nuclear Information System (INIS)

    Bartonicek, J.; Zaiss, W.; Bath, H.R.

    1999-01-01

    The relevant regulatory codes determine the ISI tasks and the time intervals for recurrent components testing for evaluation of operation-induced damaging or ageing in order to ensure component integrity on the basis of the last available quality data. In-service quality monitoring is carried out through on-line monitoring and recurrent testing. The requirements defined by the engineering codes elaborated by various institutions are comparable, with the KTA nuclear engineering and safety codes being the most complete provisions for quality evaluation and assurance after different, defined service periods. German conventional codes for assuring component integrity provide exclusively for recurrent inspection regimes (mainly pressure tests and optical testing). The requirements defined in the KTA codes however always demanded more specific inspections relying on recurrent testing as well as on-line monitoring. Foreign codes for ensuring component integrity concentrate on NDE tasks at regular time intervals, with time intervals scope of testing activities being defined on the basis of the ASME code, section XI. (orig./CB) [de

  12. Effects on in-service education on improving science teaching in Swaziland

    NARCIS (Netherlands)

    Stronkhorst, Robert; van den Akker, Jan

    2006-01-01

    This paper discusses the findings of an evaluative and interpretive study into the potential of in-service education to improve science education in Swaziland. Short-term and long-term effects of an in-service intervention are evaluated in terms of changes in classroom processes. The teaching

  13. Internal Stress Monitoring of In-Service Structural Steel Members with Ultrasonic Method.

    Science.gov (United States)

    Li, Zuohua; He, Jingbo; Teng, Jun; Wang, Ying

    2016-03-23

    Internal stress in structural steel members is an important parameter for steel structures in their design, construction, and service stages. However, it is hard to measure via traditional approaches. Among the existing non-destructive testing (NDT) methods, the ultrasonic method has received the most research attention. Longitudinal critically refracted (Lcr) waves, which propagate parallel to the surface of the material within an effective depth, have shown great potential as an effective stress measurement approach. This paper presents a systematic non-destructive evaluation method to determine the internal stress in in-service structural steel members using Lcr waves. Based on theory of acoustoelasticity, a stress evaluation formula is derived. Factor of stress to acoustic time difference is used to describe the relationship between stress and measurable acoustic results. A testing facility is developed and used to demonstrate the performance of the proposed method. Two steel members are measured by using the proposed method and the traditional strain gauge method for verification. Parametric studies are performed on three steel members and the aluminum plate to investigate the factors that influence the testing results. The results show that the proposed method is effective and accurate for determining stress in in-service structural steel members.

  14. Internal Stress Monitoring of In-Service Structural Steel Members with Ultrasonic Method

    Science.gov (United States)

    Li, Zuohua; He, Jingbo; Teng, Jun; Wang, Ying

    2016-01-01

    Internal stress in structural steel members is an important parameter for steel structures in their design, construction, and service stages. However, it is hard to measure via traditional approaches. Among the existing non-destructive testing (NDT) methods, the ultrasonic method has received the most research attention. Longitudinal critically refracted (Lcr) waves, which propagate parallel to the surface of the material within an effective depth, have shown great potential as an effective stress measurement approach. This paper presents a systematic non-destructive evaluation method to determine the internal stress in in-service structural steel members using Lcr waves. Based on theory of acoustoelasticity, a stress evaluation formula is derived. Factor of stress to acoustic time difference is used to describe the relationship between stress and measurable acoustic results. A testing facility is developed and used to demonstrate the performance of the proposed method. Two steel members are measured by using the proposed method and the traditional strain gauge method for verification. Parametric studies are performed on three steel members and the aluminum plate to investigate the factors that influence the testing results. The results show that the proposed method is effective and accurate for determining stress in in-service structural steel members. PMID:28773347

  15. Review of In-Service Inspection and Repair Technique Developments for French Liquid Metal Fast Reactors

    International Nuclear Information System (INIS)

    Baque, F.

    2005-01-01

    In-service monitoring of nuclear plants is indispensable for both the Operator and the Regulator. The notion of in-service monitoring ranges from the continuous monitoring of the reactor in operation to the thorough in-service reactor inspection during programmed shutdowns. However, the highly specific environment found in French liquid metal fast reactor plants - Phenix and Superphenix - makes monitoring and inspection complicated because of the use of a sodium coolant that is hot, opaque, and difficult to drain.The Commissariat a l'Energie Atomique, in collaboration with its traditional French partners, Electricite de France utilities and FRAMATOME/Novatome Engineering, decided to conduct a 6-yr research and development program (1994-2000) to explore this problem vis-a-vis Superphenix, as well as the possibilities of intervening within the reactor block or on components in a sodium environment. Furthermore, the safety reevaluation of Phenix, conducted between 1994 and 2003, represented an excellent 'test bench' during which the limits of inspection processes - applied to an integrated reactor concept - were surpassed using techniques such as fuel subassembly head scanning, ultrasonic examination of the core support, and visual inspection of the cover-gas plenum following a partial sodium draining. Repair techniques were investigated for cleaning of sodium wet structure surfaces, cutting of damaged parts, and welding in sodium aerosol atmosphere. Both conventional and laser processes were tested

  16. Review of activities relevant to in-service inspection

    International Nuclear Information System (INIS)

    Imanaka, N.

    1980-01-01

    Nuclear power plants are requested to provide continuing safety that cannot compare with other industries, as plant safety is a matter of much concern. To provide continuous assurance for plant safety there is increasing tendency to demand much of inspection of components during the lifetime. This inservice inspection of LMFBRs should be investigated from a view point of different systems and characteristics from LWRs. In this paper a review for inservice inspection of LMFBRs is described. To provide a continuous assurance of safety to the LMFBR, it is essential to develop how to construct the components to maintain the integrity throughout the service lifetime. Especially how to design is urged for this object. In-service inspection should be located only to compensate some uncertainty remained at the design stage, as it is too much complex in practice. As for inspection techniques, leak monitoring is assumed to be a best way to assure the plant safety continuously with the minimum plant outage time and minimum radioactive hazard to the inspectors

  17. In-Service Education of Teachers: Overview, Problems and the Way Forward

    Science.gov (United States)

    Osamwonyi, Eduwen Friday

    2016-01-01

    The need for in-service education of teachers cannot be underestimated. It is a necessity in enhancing work performance and motivation of teachers in the field. Absence of in-service training of teachers will retard professional growth of teachers as well as "missing gaps" between demands and actual achievement levels. Inservice…

  18. Assessment of diagnostic methods for determining degradation of motor-operated valves

    International Nuclear Information System (INIS)

    Haynes, H.D.; Farmer, W.S.

    1992-01-01

    The Oak Ridge National Laboratory (ORNL) has carried out a comprehensive aging assessment of motor-operated valves (MOVs) in support of the Nuclear Plant Aging Research (NPAR) program. This paper provides a summary of the ORNL MOV aging assessment with emphasis on the identification, evaluation, and application of MOV monitoring methods and techniques. The diagnostic information available from any MOV measurable parameters was evaluated by ORNL using MOVs that were mounted on test stands. Those tests led to the conclusion that the single most informative MOV measurable parameter was also the one which was most easily acquired, namely the motor current. Motor current signature analysis (MCSA) was found to provide detailed information related to the condition of the motor, motor operator, and valve across a wide range of levels. As part of the MOV aging assessment, several tests were carried out by ORNL on MOVs having implanted defects and degradations. Tests were also performed on many MOVs located within a nuclear power plant. In addition, ORNL participated in the Gate Valve Flow Interruption Blowdown Test program carried out at Wyle Laboratories in Huntsville, Alabama. Results from all of these tests are summarized in this paper and several selected examples are given. Other areas covered in this paper include descriptions of relevant regulatory issues and activities, other related diagnostics research at ORNL, and interactions ORNL has had with outside organizations for the purpose of disseminating research results

  19. Kirkpatrick evaluation model for in-service training on cardiopulmonary resuscitation

    Directory of Open Access Journals (Sweden)

    Safoura Dorri

    2016-01-01

    Full Text Available Background: There are several evaluation models that can be used to evaluate the effect of in-service training; one of them is the Kirkpatrick model. The aim of the present study is to assess the in-service training of cardiopulmonary resuscitation (CPR for nurses based on the Kirkpatrick′s model. Materials and Methods: This study is a cross-sectional study based on the Kirkpatrick′s model in which the efficacy of in-service training of CPR to nurses was assessed in the Shahadaye Lenjan Hospital in Isfahan province in 2014. 80 nurses and Nurse′s aides participated in the study after providing informed consent. The in-service training course was evaluated in reaction, learning, behavior, and results level of the Kirkpatrick model. Data were collected through a researcher-made questionnaire. Results: The mean age of the participants was 35 ± 8.5 years. The effectiveness score obtained in the reaction level (first level in the Kirkpatrick model was 4.2 ± 0.32. The effectiveness score in the second level of model or the learning level was 4.70 ± 0.09, which is statistically significant (P < 0.001. The effectiveness score at the third and fourth level were 4.1 ± 0.34 and 4.3 ± 0.12, respectively. Total effectiveness score was 4.35. Conclusions: The results of this study showed that CPR in-service training has a favorable effect on all four levels of the Kirkpatrick model for nurses and nurse′s aides.

  20. DIALOGISM, DECODING AND INTERACTIVE DIGITAL MARKETING CONCERNING THE BODILY PRACTICES IN THE ON-LINE VIDEO OLYMPIKUS.MOV FESTIVAL

    Directory of Open Access Journals (Sweden)

    Marcos Roberto Godoi

    2010-12-01

    Full Text Available The aim was to understand the meanings associated bodily practices in the videos of the festival OLYMPIKUS.MOV, and also analyze the reception/interaction Internet users on these videos. The methodology consisted the description of the videos, the selection of comments and further analysis based on the notion of dialogic language of Mikhail Bakhtin and the types of decoding Stuart Hall. We concluded that there was a large range of bodily practices and meanings related to them in the videos. Reception/interaction Internet provides a critical dialogue, congratulation, and suggestive questioning on the videos.

  1. Beijing In-Service Teachers' Self-Efficacy and Attitudes towards Inclusive Education

    Science.gov (United States)

    Malinen, Olli-Pekka; Savolainen, Hannu; Xu, Jiacheng

    2012-01-01

    Four-hundred-and-fifty-one in-service teachers from the Beijing municipality filled in a questionnaire containing a Teacher Efficacy for Inclusive Practices (TEIP) scale. The aim was to examine the factor structure of the TEIP scale among mainland Chinese in-service teachers, and to investigate the relationship between self-efficacy for inclusive…

  2. Improvement and optimization for in-service inspection of M310 nuclear power station

    International Nuclear Information System (INIS)

    Wang Chen; Sun Haitao; Gao Chen; Deng Dong

    2015-01-01

    In-service inspection (ISI) is an important method to ensure the safety of the mechanical equipment in nuclear power stations. According to the in-service inspection experience feedback from the domestic nuclear power stations, the reasonableness of some provisions in the RSE-M code are discussed and the applications of risk-informed in-service inspection (RI-ISI) are introduced, and the advices for the optimization of the ISI of the domestic M310 nuclear power stations are proposed. (authors)

  3. Knowledge and Skill Retention of In-Service versus Preservice Nursing Professionals following an Informal Training Program in Pediatric Cardiopulmonary Resuscitation: A Repeated-Measures Quasiexperimental Study

    Directory of Open Access Journals (Sweden)

    Jhuma Sankar

    2013-01-01

    Full Text Available Our objective was to compare the impact of a training program in pediatric cardiopulmonary resuscitation (CPR on the knowledge and skills of in-service and preservice nurses at prespecified time points. This repeated-measures quasiexperimental study was conducted in the pediatric emergency and ICU of a tertiary care teaching hospital between January and March 2011. We assessed the baseline knowledge and skills of nursing staff (in-service nurses and final year undergraduate nursing students (preservice nurses using a validated questionnaire and a skill checklist, respectively. The participants were then trained on pediatric CPR using standard guidelines. The knowledge and skills were reassessed immediately after training and at 6 weeks after training. A total of 74 participants—28 in-service and 46 preservice professionals—were enrolled. At initial assessment, in-service nurses were found to have insignificant higher mean knowledge scores (6.6 versus 5.8, P=0.08 while the preservice nurses had significantly higher skill scores (6.5 versus 3.2, P<0.001. Immediately after training, the scores improved in both groups. At 6 weeks however, we observed a nonuniform decline in performance in both groups—in-service nurses performing better in knowledge test (10.5 versus 9.1, P=0.01 and the preservice nurses performing better in skill test (9.8 versus 7.4, P<0.001. Thus, knowledge and skills of in-service and preservice nurses in pediatric CPR improved with training. In comparison to preservice nurses, the in-service nurses seemed to retain knowledge better with time than skills.

  4. Low Levels of Evidence on the Plastic Surgery In-Service Training Exam.

    Science.gov (United States)

    Silvestre, Jason; Bilici, Nadir; Serletti, Joseph M; Chang, Benjamin

    2016-06-01

    The Plastic Surgery In-Service Training Exam is written by the American Society of Plastic Surgeons. Examinees reasonably infer that tested material reflects the Society's vision for the core curriculum in plastic surgery. The purpose of this study was to determine the levels of evidence on which credited answers to the examination questions are based. Two recent Plastic Surgery In-Service Training Exams (2014 and 2015) were analyzed. Questions were categorized using a taxonomy model. Recommended journal article references for Level III (decision-making) questions were assigned a level of evidence. Exam sections were analyzed for differences in question taxonomy distribution and level of evidence. To look for studies with higher levels of evidence, a PubMed search was conducted for a random sample of 10 questions from each section. One hundred three Level I (25.8 percent), 138 Level II (34.5 percent), and 159 Level III (39.8 percent) questions were analyzed (p < 0.001). The hand and lower extremity section had the highest percentage of Level III questions (50.0 percent; p = 0.005). Journal articles had a mean level of evidence of 3.9 ± 0.7. The number of articles with a low level of evidence (IV and V) (p = 0.624) and the percentage of questions supported by articles with a high level of evidence (I and II) (p = 0.406) did not vary by section. The PubMed search revealed no instances of a higher level of evidence than the recommended reading list. A significant percentage of Plastic Surgery In-Service Training Exam questions test clinical management, but most are supported with a low level of evidence. Although that is consistent with low level of evidence of plastic surgery literature, educators should recognize the potential for biases of question writers.

  5. Activities with regard to research and development of technics for SNR 300 reactor vessel in-service inspection procedures

    International Nuclear Information System (INIS)

    Hoeller, K.; Kirchner, G.; Menck, J.

    1980-01-01

    During the development of SNR 300 in-service inspection equipment, several branches were tested by experiment. In this report special steps for testing of manipulation systems and additional engineering equipment for control systems, such as coupling fluid circuit or camera cooling system are considered more in detail

  6. An improved design method of a tuned mass damper for an in-service footbridge

    Science.gov (United States)

    Shi, Weixing; Wang, Liangkun; Lu, Zheng

    2018-03-01

    Tuned mass damper (TMD) has a wide range of applications in the vibration control of footbridges. However, the traditional engineering design method may lead to a mistuned TMD. In this paper, an improved TMD design method based on the model updating is proposed. Firstly, the original finite element model (FEM) is studied and the natural characteristics of the in-service or newly built footbridge is identified by field test, and then the original FEM is updated. TMD is designed according to the new updated FEM, and it is optimized according to the simulation on vibration control effects. Finally, the installation and field measurement of TMD are carried out. The improved design method can be applied to both in-service and newly built footbridges. This paper illustrates the improved design method with an engineering example. The frequency identification results of field test and original FEM show that there is a relatively large difference between them. The TMD designed according to the updated FEM has better vibration control effect than the TMD designed according to the original FEM. The site test results show that TMD has good effect on controlling human-induced vibrations.

  7. Industry standards catch up with in-service welding

    Energy Technology Data Exchange (ETDEWEB)

    Bruce, W.A.

    1999-11-01

    Welding onto a pipeline after it has been put into service, a practice commonly referred to as hot tap welding, is frequently required for several reasons. Repair sleeves are installed to reinforce areas of corrosion or mechanical damage, and branch connections are made for system modifications. There are often significant economic incentives to perform this welding without removing the system from service. Operations are maintained during welding and the pipe's contents are not vented into the atmosphere. Due to technological advances in in-service welding, industry needed an update to standards and recommended practices. This year, the American Petroleum Institute (API) hopes to meet that need. The 19th edition of API Standard 1104--Welding of Pipelines and Related Facilities, includes a new appendix that pertains to in-service welding. Appendix B, In-Service Welding, is intended to eventually replace API Recommended Practice 1107--Pipeline Maintenance Welding Practices. API 1107, which was introduced in 1966 and updated in 1987 and 1991, is intended to provide recommended practices for pipeline maintenance welding. The current third edition approached its mandatory five-year review in 1996 by the API-AGA Joint Committee on Oil and Gas Pipeline Field Welding Practices, which also maintains API 1104. The committee saw 11078 needed to reflect the updates that had been made to 1104 as well as the technological advances for in-service welding. To alleviate redundancy between the two documents, and to alleviate lag time between updates, the committee approved a proposal to update and incorporate requirements of API 1107 into an appendix of API 1104. In the meantime, the third edition of API 1107 was reapproved for another five-year review cycle.

  8. Human reliability impact on in-service inspection

    International Nuclear Information System (INIS)

    Spanner, J.C. Sr.

    1986-01-01

    This paper describes a study conducted to identify, characterize, and evaluate the human reliability aspects of ultrasonic testing/inservice inspection (UT/ISI). Recent measurements of UT/ISI system effectiveness have revealed wide variations in performance; suggesting that insufficient emphasis is being placed on the human reliability aspects of nondestructive examination. It appears that NDE performance can be improved through application of the human factors principles relating to the task, training, procedure, environmental, and individual difference variables. These variables are collectively referred to as performance-shaping factors. A man-machine systems model was developed to describe the UT/ISI process using functional task descriptors. The relative operating characteristic (ROC) analysis method, which is derived from signal detection theory, offers unique attributes for analyzing NDT performance. The results of a limited human factors evaluation conducted in conjunction with a mini-round robin test are also described

  9. Effect of Titanium on the Microstructure and Mechanical Properties of High-Carbon Martensitic Stainless Steel 8Cr13MoV

    OpenAIRE

    Wen-Tao Yu; Jing Li; Cheng-Bin Shi; Qin-Tian Zhu

    2016-01-01

    The effect of titanium on the carbides and mechanical properties of martensitic stainless steel 8Cr13MoV was studied. The results showed that TiCs not only acted as nucleation sites for δ-Fe and eutectic carbides, leading to the refinement of the microstructure, but also inhibited the formation of eutectic carbides M7C3. The addition of titanium in steel also promoted the transformation of M7C3-type to M23C6-type carbides, and consequently more carbides could be dissolved into the matrix duri...

  10. Increasing the Effectiveness of Inservice Training for Desegregation: A Synthesis of Current Research. Reference & Resource Series.

    Science.gov (United States)

    Smylie, Mark A.; Hawley, Willis D.

    This report reviews recent research on strategies that have been found to promote useful and effective inservice training programs in desegregated schools. The first section presents approaches for planning and implementing inservice training for desegregation. The second section describes inservice desegregation training programs that focus on:…

  11. In-service examination of IHX tubing with eddy current NDT equipment

    International Nuclear Information System (INIS)

    Brown, R.L.

    1972-01-01

    Single and multiple frequency eddy current (ET) nondestructive testing (NDT) techniques and equipment were investigated for in-service inspection of sodium-contaminated intermediate heat exchanger (IHX) tubing. A four frequency technique, demonstrated in the laboratory, was relatively insensitive to signals caused by probe motion, tube support plates, and residual sodium on the outer surface of the tubes. No method was found to avoid the signals from residual sodium on the inside surfaces of the tube. (U.S.)

  12. Scientific foundation of in-service training for prevention of peer violence

    Directory of Open Access Journals (Sweden)

    Pavlović Miroslav V.

    2016-01-01

    Full Text Available The paper analyzes the compatibility of the continuous in-service teacher training for prevention of peer violence and modern scientific knowledge in this area. The first part of the paper summarizes the results of 12 systematic reviews and meta-analyses of the effectiveness of the studies of antibullying programs published since 2000. which relate to the effects of uni-modal and multi-modal programs, and the efficacy of interventions used in anti-bullying programs. The second part of the paper analyses the approved programs of in-service teacher training, in which priority is given to the prevention of violence, abuse and negligence. We analyzed 39 programs of continuous in-service teacher training, and focused on the empirical bases of the programs (researches which confirm the effectiveness of a program and the contents of the training (the level of preventive activity, modality, field, and interventions. The results of the analysis of the programs of continuous in-service training for peer violence prevention are discussed in the context of modern scientific knowledge of effectiveness of anti-bullying programs and of professional development of teachers and counsellors.

  13. Periodic and in-service inspection programs

    International Nuclear Information System (INIS)

    Dinu, M.

    2000-01-01

    Periodic and in-service inspection programs for Cernavoda NPP consists of periodic inspections of CANDU NPP components CSAN N-285.4 and CSAN N-285.4, in-service inspections and repair and modifications general inspection. Periodic inspection program document (PIPD) determines the systems and components subject to inspection, the category of the inspection, techniques, areas and other details.The current status of the inspection programs is presented, including containment , erosion/corrosion, pressure vessel support and snubbers, main steam lines inspection programs. Qualification program in Cernavoda NPP involves equipment qualification in the on-site laboratory, yearly certification, special equipment qualification in the National Institute of Metrology. All procedures are approved by the ISCIR (regulatory body for pressure vessel and lifting equipment) and CNCAN (National Commission on Nuclear Activities Control). Qualification of the personnel is performed according to the ISCIR Technical prescription CR 11/82 for up to 3 year period. Final qualification and licensing is performed by CNCAN

  14. Evaluation of computer-based ultrasonic inservice inspection systems

    International Nuclear Information System (INIS)

    Harris, R.V. Jr.; Angel, L.J.; Doctor, S.R.; Park, W.R.; Schuster, G.J.; Taylor, T.T.

    1994-03-01

    This report presents the principles, practices, terminology, and technology of computer-based ultrasonic testing for inservice inspection (UT/ISI) of nuclear power plants, with extensive use of drawings, diagrams, and LTT images. The presentation is technical but assumes limited specific knowledge of ultrasonics or computers. The report is divided into 9 sections covering conventional LTT, computer-based LTT, and evaluation methodology. Conventional LTT topics include coordinate axes, scanning, instrument operation, RF and video signals, and A-, B-, and C-scans. Computer-based topics include sampling, digitization, signal analysis, image presentation, SAFI, ultrasonic holography, transducer arrays, and data interpretation. An evaluation methodology for computer-based LTT/ISI systems is presented, including questions, detailed procedures, and test block designs. Brief evaluations of several computer-based LTT/ISI systems are given; supplementary volumes will provide detailed evaluations of selected systems

  15. Apparative developments for inservice inspections of reactor pressure vessels

    International Nuclear Information System (INIS)

    Bohn, H.; Ruthrof, K.; Barbian, O.A.; Kappes, W.; Neumann, R.; Stanger, H.K.

    1987-01-01

    Emphasizing PWR pressure vessel (RPV) inspections, recent developments of new generations of automated and mechanized ultrasonic inspection equipment are presented. Starting from general equipment design and inservice implenentation criteria, specific examples are given. Main attention is directed to equipment realization of phased array and ALOK inspection techniques, especially in their combination. Refined aspects of subsequent computer processing and evaluation of defect detection data are described. Analytical features and potential for further developments become evident. Remote controlled RPV inspections are stressed by describing a new generation of central mast manipulators, forming an integral part of total inservice inspection system. (orig./HP)

  16. Motor-operated valve (MOV) actuator motor and gearbox testing

    International Nuclear Information System (INIS)

    DeWall, K.; Watkins, J.C.; Bramwell, D.

    1997-07-01

    Researchers at the Idaho National Engineering and Environmental Laboratory tested the performance of electric motors and actuator gearboxes typical of the equipment installed on motor-operated valves used in nuclear power plants. Using a test stand that simulates valve closure loads against flow and pressure, the authors tested five electric motors (four ac and one dc) and three gearboxes at conditions a motor might experience in a power plant, including such off-normal conditions as operation at high temperature and reduced voltage. They also monitored the efficiency of the actuator gearbox. All five motors operated at or above their rated starting torque during tests at normal voltages and temperatures. For all five motors, actual torque losses due to voltage degradation were greater than the losses calculated by methods typically used for predicting motor torque at degraded voltage conditions. For the dc motor the actual torque losses due to elevated operating temperatures were greater than the losses calculated by the typical predictive method. The actual efficiencies of the actuator gearboxes were generally lower than the running efficiencies published by the manufacturer and were generally nearer the published pull-out efficiencies. Operation of the gearbox at elevated temperature did not affect the operating efficiency

  17. Morphology and Performance of 5Cr5MoV Casting Die Steel in the Process of Surfacing

    Science.gov (United States)

    Song, Yulai; Kong, Xiangrui; Yang, Pengcong; Fu, Hongde; Wang, Xuezhu

    2017-12-01

    To investigate the microstructures and mechanical properties of the deposited metal on surface of die steel, two layer of weld-seam were prepared on the surface of 5Cr5MoV die steel by arc surfacing. The surface microstructures and microhardness were characterized by scanning electron microscopy, energy dispersive spectrometer and Vickers microhardness tester, respectively. The effect of load on the abrasion resistance and wear mechanism of the base metal and surfacing metal was studied by pin-on-disk tribometer. The results showed that martensite and retained austenite exist in weld-seam, both of them grow up in the form of dendrites and equiaxed grains and microhardness reach 774.2HV. The microstructures of the quenching zone mainly consist of martensite and retained austenite, while tempered martensite is the dominant phase in partial quenching zone. The abrasion resistance of the surfacing metal is superior to the base metal based on the results of wear test. The wear rates of surfacing metal and base metal raise with the increase of load. The wear rates of base metal raise extremely when the load reach 210N. Both of two kinds of materials have the similar wear mechanism, namely, abrasive wear at low load, oxidative wear and adhesive wear at high load.

  18. French developments and experience in the field of inservice inspection

    International Nuclear Information System (INIS)

    Saglio, Robert; Destribats, M.-T.; Pigeon, Michel; Roule, Maurice; Touffait, A.-M.

    1979-01-01

    The French PWR nuclear plant program was at the origin of a large amount of R and D work in the field of inservice inspection. The actions which were undertaken may be split up into different levels: - the regulatory level, the R and D level, the design level, the flaw evaluation level. The first results of pre and inservice inspections are presented. The experience gained by French Atomic Energy Commission with new techniques like focussed ultrasonics transducers and multi frequencies Eddy current apparatus are discussed

  19. Rapid repair advisor for motor-operated valves

    International Nuclear Information System (INIS)

    Somsel, J.K.

    1991-01-01

    This paper reports on the initial proposed application for the Rapid Repair Advisor project for motor-operated valves (MOVs). The expected benefits from an MOV testing expert system depend on the purpose of the testing. Straight acceptance testing (post-maintenance and surveillance) could benefit from field verification of test validity. Troubleshooting of failed operators is seldom difficult. Intermittent problems are difficult to resolve suggesting that trace recording capabilities are needed. Predictive diagnosis places the most demands on the interpretive skills of the engineer. However, the limit to predictive capabilities seems to lie in the design of the MOV and the measurable parameters. Utilities are expected to require a knowledgeable MOV maintenance engineer to make decisions on MOV maintenance and operability. The economics of developing an expert system are comparable to improved training for the end-users

  20. In-service inspection guidelines for composite aerospace structures

    International Nuclear Information System (INIS)

    Heida, Jaap H.; Platenkamp, Derk J.

    2012-01-01

    The in-service inspection of composite aerospace structures is reviewed, using the results of a evaluation of promising, mobile non-destructive inspection (NDI) methods. The evaluation made use of carbon fibre reinforced specimens representative for primary composite aerospace structures, including relevant damage types such as impact damage, delaminations and disbonds. A range of NDI methods were evaluated such as visual inspection, vibration analysis, phased array ultrasonic inspection, shearography and thermography inspection. Important aspects of the evaluation were the capability for defect detection and characterization, portability of equipment, field of view, couplant requirements, speed of inspection, level of training required and the cost of equipment. The paper reviews the damage tolerance design approach for composites, and concludes with guidelines for the in-service inspection of composite aerospace structures.

  1. An In-Service: Microcomputers and Their Practical Application Levels in the Educational Process.

    Science.gov (United States)

    Webb, Rosanna M.; Karr-Kidwell, PJ

    Intended for both preservice and inservice teachers at all levels, the inservice workshop detailed in this report focuses on the computer as an educational tool that can be utilized without gaining an expertise in the inner workings and technicalities associated with the machinery. Related equipment and terminology is introduced informally to…

  2. Qualification of UT methods and systems used for in-service inspections of VVER 440 vessels

    International Nuclear Information System (INIS)

    Skala, Z.; Vit, J.

    2003-01-01

    SKODA JS has been performing automated in-service inspections VVER reactor pressure vessels for more than twenty years. All of these inspections were performed by ultrasonic pulse echo method, combined from 1996 with eddy current testing. The Time of Flight Diffraction Method (TOFD) is one of modern methods of ultrasonic testing. The accuracy of sizing the through wall extent of a flaw by TOFD is much better than the accuracy achievable by the pulse echo method. A series of laboratory tests were performed by SKODA JS and confirmed the suitability of TOFD method for VVER reactor parts testing. The Czech Atomic law demands the qualification of systems and methods used for the in-service inspections of nuclear reactors. The qualification is done in accordance with ENIQ methodology and consists of preparation of the Technical Justification and practical tests made under the surveillance of Qualification Body. SKODA JS intends to qualify systems and methods used for the automated ultrasonic testing of VVER 440 and VVER 1000 reactor components from the inner as well as from the outer surface. The accuracy of the flaw through wall extent sizing by TOFD was confirmed by the qualification of methods and systems used for the testing of VVER 440 vessel circumferential weld and so the TOFD method shall be used routinely by SKODA JS for the inspection of vessel circumferential welds root area and for sizing of flaws exceeding the acceptance level. (author)

  3. Alternate Welding Processes for In-Service Welding

    Science.gov (United States)

    2009-04-24

    Conducting weld repairs and attaching hot tap tees onto pressurized pipes has the advantage of avoiding loss of service and revenue. However, the risks involved with in-service welding need to be managed by ensuring that welding is performed in a rep...

  4. The Impact of a Summer Institute on Inservice Early Childhood Teachers' Knowledge of Earth and Space Science Concepts

    Science.gov (United States)

    Sackes, Mesut; Trundle, Kathy Cabe; Krissek, Lawrence A.

    2011-01-01

    This study investigated inservice PreK to Grade two teachers' knowledge of some earth and space science concepts before and after a short-term teacher institute. A one-group pre-test-post-test design was used in the current study. Earth science concepts targeted during the professional development included properties of rocks and soils, and the…

  5. Probing Pre-and In-Service Physics Teachers' Knowledge Using the Double-Slit Thought Experiment

    Science.gov (United States)

    Asikainen, Mervi A.; Hirvonen, Pekka E.

    2014-01-01

    This study describes the use of the double-slit thought experiment as a diagnostic tool for probing physics teachers' understanding. A total of 9 pre-service teachers and 18 in-service teachers with a variety of different experience in modern physics teaching at the upper secondary level responded in a paper-and-pencil test and three of these…

  6. In-service inspection of nuclear power plants

    International Nuclear Information System (INIS)

    1991-01-01

    This Manual is intended to provide more comprehensive considerations on the management, organization, preparation, improvement and implementation of in-service inspection activities and the related surveillance. It also gives illustrative examples of good practices and recommendations from operating and other organizations that are consistent with the requirements and recommendations of the Code and Safety Guides. The Manual is directed primarily towards plant management. This Manual should be used in conjunction with the Code and the Safety Guides, in particular with IAEA Safety Series Nos. 50-C-O, 50-SG-O2, 50-SG-05, 50-SG-07, 50-SG-08 and 50-SG-D1, which contain recommendations of a general character about maintenance activities and radiation protection in an operating power plant, and with the 'Manual on the Maintenance of Systems and Components Important to Safety'. This Manual is divided into four technical sections. The first introduces the purpose, structure and main requirements of the programme. The second section describes constituents of the programme, recommending its scope, scheduling, acceptance standards and documentation of results. The following section goes into details of the inspection programme's contents, such as the selection of components, inspection locations, defect types, applicable techniques and procedures, and the evaluation of results. The last section specifies recommended methods and techniques for inspection, such as visual, ultrasonic, eddy current, magnetic particle and others. This main part of the Manual is complemented by a number of annexes which reproduce actual national examples of established procedures, ISI programme parts, acceptance standards, personnel training programmes, testing techniques and other aspects of in-service inspection, illustrating practical implementation of the recommendations of the Manual

  7. Physics teachers' nuclear in-service training in Hungary

    International Nuclear Information System (INIS)

    Ujvari, Sandor

    2005-01-01

    Teaching of science subjects, specifically physics among others, is important in Hungarian schools. The paper starts with some historical aspects on how the modern physics reached Hungarian schools, what kinds of methods the physics teachers use for their in-service training and what is their success. In 1985 Hungarian Government introduced the system of physics teacher's in-service training for a year. The courses end with a thesis and examination. Teachers have a possibility to join the nuclear physics intensive course of Nuclear Physics Department at Eottvos University. Curriculum and topics of laboratory practice are given together with some dissertations of the course. Moreover, several competition (Leo Szilard competition) is mentioned with starting that in each year the 5 best students get free entrance to the Hungarian universities. (S. Ohno)

  8. Qualifying in-service education of Science Teachers (QUEST)

    DEFF Research Database (Denmark)

    Nielsen, Keld; Nielsen, Birgitte Lund; Pontoppidan, Birgitte

    The Danish QUEST-project is a large-scale (450 teachers), long-term (4 years) professional development project for science teachers. The project aims at closing the gap between the present inconsequential practice in in-service education and recent research results documenting conditions for effe......The Danish QUEST-project is a large-scale (450 teachers), long-term (4 years) professional development project for science teachers. The project aims at closing the gap between the present inconsequential practice in in-service education and recent research results documenting conditions...... and peer involvement in collaborative practices in the school science teacher group is specifically addressed and targeted throughout the project. A special way of working (the QUEST-Rhythm) has been developed to increase the degree of teacher collaboration and networking over the 4 years. The accompanying...

  9. Application of reliability-centered maintenance to boiling water reactor emergency core cooling systems fault-tree analysis

    International Nuclear Information System (INIS)

    Choi, Y.A.; Feltus, M.A.

    1995-01-01

    Reliability-centered maintenance (RCM) methods are applied to boiling water reactor plant-specific emergency core cooling system probabilistic risk assessment (PRA) fault trees. The RCM is a technique that is system function-based, for improving a preventive maintenance (PM) program, which is applied on a component basis. Many PM programs are based on time-directed maintenance tasks, while RCM methods focus on component condition-directed maintenance tasks. Stroke time test data for motor-operated valves (MOVs) are used to address three aspects concerning RCM: (a) to determine if MOV stroke time testing was useful as a condition-directed PM task; (b) to determine and compare the plant-specific MOV failure data from a broad RCM philosophy time period compared with a PM period and, also, compared with generic industry MOV failure data; and (c) to determine the effects and impact of the plant-specific MOV failure data on core damage frequency (CDF) and system unavailabilities for these emergency systems. The MOV stroke time test data from four emergency core cooling systems [i.e., high-pressure coolant injection (HPCI), reactor core isolation cooling (RCIC), low-pressure core spray (LPCS), and residual heat removal/low-pressure coolant injection (RHR/LPCI)] were gathered from Philadelphia Electric Company's Peach Bottom Atomic Power Station Units 2 and 3 between 1980 and 1992. The analyses showed that MOV stroke time testing was not a predictor for eminent failure and should be considered as a go/no-go test. The failure data from the broad RCM philosophy showed an improvement compared with the PM-period failure rates in the emergency core cooling system MOVs. Also, the plant-specific MOV failure rates for both maintenance philosophies were shown to be lower than the generic industry estimates

  10. In-Service Education: A Blueprint for Action

    Science.gov (United States)

    Keller, Arnold J.

    1978-01-01

    Inservice teacher education is the logical catalyst to any process of school improvement but school board members and school administrators must insure that their forthcoming efforts fulfill three important criteria: (1) Shared decision-making responsibilities with recognized representatives of the teaching staff, preferably at the individual…

  11. Primary Teachers' Particle Ideas and Explanations of Physical Phenomena: Effect of an In-Service Training Course

    Science.gov (United States)

    Papageorgiou, George; Stamovlasis, Dimitrios; Johnson, Phil Michael

    2010-01-01

    This paper presents a study concerning Greek primary school teachers' (n = 162) ideas about the particulate nature of matter and their explanations of physical phenomena. The study took place during an in-service training course where the effectiveness of a specially designed intervention was tested. A key feature was an approach based on the…

  12. Risk informed In-service Inspection

    International Nuclear Information System (INIS)

    Corak, Z.

    2003-01-01

    Safety of nuclear power plants is one of the most important conditions for their acceptance. Safety is being acheived by numerous methods and techniques in phase of design, manufacturing and maintenance of the nuclear power plants. In-service Inspection (ISI) has a significant role in avoidances of failure in components of nuclear power plants just the same as in assurance of their integrity. Non-destructive examinations are performed periodically in accordance with 10 CFR 50 50.55a and ASME Boiler and Pressure Vessel Code section XI which is referenced by 10 CFR 50.55a. Nondestructive examinations provide information about a current condition of equipment at nuclear power plants and about any damage, defect or degradation mechanism. A lot of effort is often spent in situations in which the probability of failure and their effects on safety have a very low impact. Practical experience shows that failures can often occur at locations where the inspection has never been performed. Costs and expenses of in-service inspections are very high. Therefore, the accent has to be on locations with significant risk to safety. Many years of nuclear power plants' operation and maintenance have resulted in a more broad knowledge of degradation mechanism and the most susceptible locations and huge databases of different nuclear power plants' components. U.S. Nuclear Regulatory Commission (NRC) and the nuclear industry have recognized that probabilistic risk assessment (PRA) has developed and changed to be more useful in improvement of traditional engineering approaches in nuclear power plants regulation. After the publication of its policy statement on the use of PRA in nuclear regulatory activities, the Commission ordered the NRC staff to develop a regulatory framework that incorporated risk insights. The American Society of Mechanical Engineers (ASME) initiated Code Case N-560, N-577, and N-578 that address the importance of categorization and inspection of piping using risk

  13. Inservice inspection procedures and training according to the ASME code

    International Nuclear Information System (INIS)

    Greenwald, S.M.; Chockie, L.J.

    1987-01-01

    Mandatory training of the technical staff at a nuclear power plant is of paramount importance if we are to avoid costly plant shutdowns. This training should include the requirements for both Preservice and Inservice Inspection, in addition to Quality Assurance procedures as required by the American Society of Mechanical Engineers (ASME) Code. The training is best accomplished by utilizing instructors who are thoroughly familiar with plant operations and the ASME Code, as well as serving on one of the Code committees. This paper focuses on the Inservice Inspection procedures and the results of an intensive training effort to implement such procedures. (author)

  14. Empowering Education: A New Model for In-service Training of Nursing Staff.

    Science.gov (United States)

    Chaghari, Mahmud; Saffari, Mohsen; Ebadi, Abbas; Ameryoun, Ahmad

    2017-01-01

    In-service training of nurses plays an indispensable role in improving the quality of inpatient care. Need to enhance the effectiveness of in-service training of nurses is an inevitable requirement. This study attempted to design a new optimal model for in-service training of nurses. This qualitative study was conducted in two stages during 2015-2016. In the first stage, the Grounded Theory was adopted to explore the process of training 35 participating nurses. The sampling was initially purposeful and then theoretically based on emerging concept. Data were collected through interview, observation and field notes. Moreover, the data were analyzed through Corbin-Strauss method and the data were coded through MAXQDA-10. In the second stage, the findings were employed through 'Walker and Avants strategy for theory construction so as to design an optimal model for in-service training of nursing staff. In the first stage, there were five major themes including unsuccessful mandatory education, empowering education, organizational challenges of education, poor educational management, and educational-occupational resiliency. Empowering education was the core variable derived from the research, based on which a grounded theory was proposed. The new empowering education model was composed of self-directed learning and practical learning. There are several strategies to achieve empowering education, including the fostering of searching skills, clinical performance monitoring, motivational factors, participation in the design and implementation, and problem-solving approach. Empowering education is a new model for in-service training of nurses, which matches the training programs with andragogical needs and desirability of learning among the staff. Owing to its practical nature, the empowering education can facilitate occupational tasks and achieving greater mastery of professional skills among the nurses.

  15. In-Service Preschool Teachers' Thoughts about Technology and Technology Use in Early Educational Settings

    Science.gov (United States)

    Kara, Nuri; Cagiltay, Kursat

    2017-01-01

    The purpose of this study is to understand in-service preschool teachers' thoughts about technology and technology use in early educational settings. Semi-structured interviews were conducted with 18 in-service preschool teachers. These teachers were selected from public and private preschools. Convenient sampling was applied because teachers who…

  16. A General Investigation of the In-Service Training of English Language Teachers at Elementary Schools in Turkey

    Directory of Open Access Journals (Sweden)

    Ebru Melek KOÇ

    2016-03-01

    Full Text Available This study presents a critical diagnosis of in-service teacher-training activities offered to English-language teachers in Turkey and aims to investigate whether those teachers are satisfied with the activities. Thirty-two English-language teachers participated in this study. Data were collected from 32 elementary-school teachers of English as a foreign language, using a general evaluation form prepared by the researcher. The results indicate that the teachers are not satisfied with their in-service teacher-training activities and that in-service training does not fulfil their needs. The study also proposes an in-service teacher training model in distance format.

  17. Advanced Approach of Reactor Pressure Vessel In-service Inspection

    International Nuclear Information System (INIS)

    Matokovic, A.; Picek, E.; Pajnic, M.

    2006-01-01

    The most important task of every utility operating a nuclear power plant is the continuously keeping of the desired safety and reliability level. This is achieved by the performance of numerous inspections of the components, equipment and system of the nuclear power plant in operation and in particular during the scheduled maintenance periods at re-fueling time. Periodic non-destructive in-service inspections provide most relevant criteria of the integrity of primary circuit pressure components. The task is to reliably detect defects and realistically size and characterize them. One of most important and the most extensive examination is a reactor pressure vessel in-service inspection. That inspection demand high standards of technology and quality and continual innovation in the field of non-destructive testing (NDT) advanced technology as well as regarding reactor pressure vessel tool and control systems. A remote underwater contact ultrasonic technique is employed for the examination of the defined sections (reactor welds), whence eddy current method is applied for clad surface examinations. Visual inspection is used for examination of the vessel inner surface. The movement of probes and data positioning are assured by using new reactor pressure vessel tool concept that is fully integrated with NDT systems. The successful performance is attributed thorough pre-outage planning, training and successful performance demonstration qualification of chosen NDT techniques on the specimens with artificial and/or real defects. Furthermore, use of advanced approach of inspection through implementation the state of the art examination equipment significantly reduced the inspection time, radiation exposure to examination personnel, shortening nuclear power plant outage and cutting the total inspection costs. The advanced approach as presented in this paper offer more flexibility of application (non-destructive tests, local grinding action as well as taking of boat samples

  18. In-service thermal ageing of martensitic stainless steels

    International Nuclear Information System (INIS)

    Tampigny, R.; Molinie, E.; Foct, F.; Dignocourt, P.

    2011-01-01

    Martensitic stainless steels are largely used in Nuclear Power Plants (NPPs) mainly as valve stems, bolts or nuts due to their high mechanical properties and their good resistance to corrosion in primary water. At the end of the eighties, research studies have demonstrated a thermal ageing irreversible embrittlement due to the precipitation of a chromium-rich phase for X6 CrNiCu 17-04, X6 CrNiMo 16.04 and X12 Cr 13 martensitic stainless steels and a semi-empirical modeling has been proposed. Numerous metallurgical examinations have been performed in hot laboratories to consolidate the good correlation between in-service experience and the modeling developed by EDF RD. According to the feedback analysis, thermal ageing embrittlement can appear at different in-service temperatures or do not appear in relation with chemical composition of martensitic stainless steels and end of manufacturing heat treatments associated. A new campaign of metallurgical examinations has been proposed to consolidate previous studies and to contribute to maintenance policy for the next ten years after the third decennial outages for 900 MWe NPP. Influence of real in-service temperatures and end of manufacturing heat treatments have been examined to understand reasons why in some cases thermal ageing embrittlement does not occur or occur with a lowest intensity. These new results have contributed to reinforce EDF RD modeling validity and technical specifications defined in RCC-M for new valve stems, bolts or nuts. (authors)

  19. Addressing Adolescent Depression in Schools: Evaluation of an In-Service Training for School Staff in the United States

    Science.gov (United States)

    Valdez, Carmen R.; Budge, Stephanie L.

    2012-01-01

    This study evaluated an adolescent depression in-service training for school staff in the United States. A total of 252 school staff (e.g., teachers, principals, counselors) completed assessments prior to and following the in-service and a subsample of these staff participated in focus groups following the in-service and three months later.…

  20. Reactor safety through quality assurance and in-service inspection

    International Nuclear Information System (INIS)

    Bush, S.H.

    The quality assurance is discussed of nuclear power plant equipment with respect to the following regulations: section 50 10 CFR - supplement B, section NA-400, ASME - section III and ANSI N-54.2. Quality assurance and reliability are assessed with regard to two aspects: all preoperational functions and all operating stages of the power plant. During the production of nuclear power plant components, increased attention should be devoted to the choice of material, materials testing, production programme and to the production process. During power plant operation, care should be given to periodical in-service inspections which guarantee the plant reliability; defects should immediately be remedied or the power plant shut down. Emphasis is put on the tests of reactor welded joints in compliance with the ASME code. The results of operating tests are used as feedback in the design and testing of the components during production. The probabilities were calculated of the occurrence and elimination of defects during the manufacture and operation of a nuclear reactor. (J.B.)

  1. Pre-Service and In-Service Preschool Teachers' Views Regarding Creativity in Early Childhood Education

    Science.gov (United States)

    Alkus, Simge; Olgan, Refika

    2014-01-01

    This research investigated the views of pre-service and in-service preschool teachers concerning the developing of children's creativity in early childhood education by determining the similarities and/or differences among their views. The data were gathered from 10 pre-service and 11 in-service teachers through focus group meetings, and then from…

  2. Evaluations of Structural Failure Probabilities and Candidate Inservice Inspection Programs

    Energy Technology Data Exchange (ETDEWEB)

    Khaleel, Mohammad A.; Simonen, Fredric A.

    2009-05-01

    The work described in this report applies probabilistic structural mechanics models to predict the reliability of nuclear pressure boundary components. These same models are then applied to evaluate the effectiveness of alternative programs for inservice inspection to reduce these failure probabilities. Results of the calculations support the development and implementation of risk-informed inservice inspection of piping and vessels. Studies have specifically addressed the potential benefits of ultrasonic inspections to reduce failure probabilities associated with fatigue crack growth and stress-corrosion cracking. Parametric calculations were performed with the computer code pc-PRAISE to generate an extensive set of plots to cover a wide range of pipe wall thicknesses, cyclic operating stresses, and inspection strategies. The studies have also addressed critical inputs to fracture mechanics calculations such as the parameters that characterize the number and sizes of fabrication flaws in piping welds. Other calculations quantify uncertainties associated with the inputs calculations, the uncertainties in the fracture mechanics models, and the uncertainties in the resulting calculated failure probabilities. A final set of calculations address the effects of flaw sizing errors on the effectiveness of inservice inspection programs.

  3. RASI Update: Research for RA In-Service Education.

    Science.gov (United States)

    Dickson, Gary L.; And Others

    1981-01-01

    Reports results of applied research with the Resident Assistant Stress Inventory. Concluded that sex, personality, job performance, experience, stress management training, and housing characteristics affect perceived anxiety among resident assistants. Suggests additional research is needed for planning inservice education programs. (JAC)

  4. Risk-informed importance analysis of in-service testing components for Ulchin units 3 and 4

    International Nuclear Information System (INIS)

    Kang, D. I.; Kim, K. Y.; Ha, J. J.

    2001-01-01

    In this paper, we perform risk-informed importance analysis of in-service tesing (IST) components for Ulchin Units 3 and 4. The importance analysis using PSA is performed through Level 1 internal and external, shutdown/low power operation, and Level 2 internal PSA. The sensitivity analysis is also performed. For the components not modeled in PSA logic, we develop and apply a new integrated importance analysis method. The importance analysis results for IST valves show that 167 (26.55%) of 629 IST valves are HSSCs and 462 (73.45%) are LSSCs. The importance analysis results for IST pumps show that 28 (70%) of 40 IST pumps are HSSCs and 12 (30%) are KSSCs

  5. Development of RETRAN-03/MOV code for thermal-hydraulic analysis of nuclear reactor under moving conditions

    International Nuclear Information System (INIS)

    Kim, Hak Jae; Park, Goon Cherl

    1996-01-01

    Nuclear ship reactors have several; features different from land-based PWR's. Especially, effects of ship motions on reactor thermal-hydraulics and good load following capability for abrupt load changes are essential characteristics of nuclear ship reactors. This study modified the RETRAN-03 to analyze the thermal-hydraulic transients under three-dimensional ship motions, named RETRAN-03/MOV in order to apply to future marine reactors. First Japanese nuclear ship MUTSU reactor have been analyzed under various ship motions to verify this code. Calculations have been performed under rolling,heaving and stationary inclination conditions during normal operation. Also, the natural circulation has been analyzed, which can provide the decay heat removed to ensure the passive safety of marine reactors. As results, typical thermal-hydraulic characteristics of marine reactors such as flow rate oscillations and S/G water level oscillations have been successfully simulated at various conditions. 7 refs., 11 figs. (author)

  6. Conceptual design of in-service inspection and maintenance for KALIMER

    International Nuclear Information System (INIS)

    Ju, Y. S.; Kim, S. H.; Koo, K. H.; You, B.

    1999-01-01

    In-service inspection and maintenance are very important for the safety and availability of nuclear power plants. The conceptual requirements of in-service inspection and maintenance should be reflected in the earlier design process for the verification of the plant operability and reliability. In this paper the fundamental approaches of the inspection and maintenance for KALIMER are established to ensure the structural integrity and operability for KALIMER. The general strategy and methodology of maintenance and inspection for the reactor system and components are proposed and described for satisfying the intents of the Section XI, Division 3, of ASME code and considering the design characteristics of KALIMER

  7. Empowering education: A new model for in-service training of nursing staff

    Directory of Open Access Journals (Sweden)

    MAHMUD CHAGHARI

    2017-01-01

    Full Text Available Introduction: In-service training of nurses plays an indispensable role in improving the quality of inpatient care. Need to enhance the effectiveness of in-service training of nurses is an inevitable requirement. This study attempted to design a new optimal model for in-service training of nurses. Methods: This qualitative study was conducted in two stages during 2015-2016. In the first stage, the Grounded Theory was adopted to explore the process of training 35 participating nurses. The sampling was initially purposeful and then theoretically based on emerging concept. Data were collected through interview, observation and field notes. Moreover, the data were analyzed through Corbin-Strauss method and the data were coded through MAXQDA-10. In the second stage, the findings were employed through Walker and Avant’s strategy for theory construction so as to design an optimal model for in-service training of nursing staff. Results: In the first stage, there were five major themes including unsuccessful mandatory education, empowering education, organizational challenges of education, poor educational management, and educational-occupational resiliency. Empowering education was the core variable derived from the research, based on which a grounded theory was proposed. The new empowering education model was composed of self-directed learning and practical learning. There are several strategies to achieve empowering education, including the fostering of searching skills, clinical performance monitoring, motivational factors, participation in the design and implementation, and problem-solving approach. Conclusion: Empowering education is a new model for in-service training of nurses, which matches the training programs with andragogical needs and desirability of learning among the staff. Owing to its practical nature, the empowering education can facilitate occupational tasks and achieving greater mastery of professional skills among the nurses.

  8. An Assessment of In-Service Training Needs of Elementary Administrators. A Topic of Study.

    Science.gov (United States)

    Parks, James Richard

    The problem addressed in this topic of study was that of identifying the inservice training needs of 26 administrators in the Glendale (Arizona) Elementary District and ranking those needs in order of importance. It was assumed that by ranking topic areas according to the number and percentage of responses a priority list of inservice training…

  9. Study on in-service inspection methods for the above-ground oil tanks floors

    Energy Technology Data Exchange (ETDEWEB)

    Min Xiong; Yewei Kang; Mingchun, Lin; Yi Sun [PetroChina Pipeline R and D Center, Langfang (China)

    2009-07-01

    It is very dangerous to the environment when oil tank floors get corrosion or leak during its long-time service. The traditional inspection methods need to shut down a tank and to empty it, then to clean it in order to inspect the floor. Comparing with the traditional methods, the in-service methods can inspect tank floors rapidly without removing product and opening the tank and can save many costs of tank emptying and cleaning. This paper explores three up-to date in-service inspection methods for the oil tank floors which are acoustic emission technology ultrasonic guided wave technology and mobile robot technology. The theoretic foundation and application status of each method is described. The advantage and disadvantage of each in-service detection technology is concluded. At last some proposals are made. (author)

  10. Targeted In-service Inspections Using Risk Insights

    International Nuclear Information System (INIS)

    Kulat, S.; Montgomery, B.; Robin Graybeal, M.

    2012-01-01

    This paper includes a discussion of the historical background and rationale for development of a targeted In-service Inspection (ISI) program using risk insights, known as Risk-Informed In-service Inspection (RI-ISI). RI-ISI programs are optimized inspection programs which target specific welds for inspection based upon potential degradation mechanisms and consequences of failure. Inspections are performed on those welds that are the highest contributors to plant risk. Additionally the inspections are tailored to detect the specific postulated degradation mechanisms. As a result, the numbers of inspections are reduced along with the associated cost and radiation exposure, while maintaining or improving the level of quality and safety. Provided in this paper are the basic principles of RI-ISI program development, and a summary of the impact of the implementation of such programs. For example, implementation of a Risk-Informed In-service Inspection program results in a reduction of both cost and radiation exposure. Cost savings are estimated at between USD 1,000,000 and USD 2,300,000 per unit per ten year interval for a Class 1 and2 RI-ISI application. Cost savings are estimated based on average cost per weld of USD 7600 for examination, including the following activities: erection and removal of scaffolding, removal and replacement of insulation, removal and replacement of interferences, weld preparation, examination, documentation, craft support. Reduction in radiation exposure is estimated at 75% to 90% for a Class 1 and2 RI-ISI application. Reduction in radiation exposure is due to the following factors: number of welds selected for examination decreases by 60% to 75%, surface examinations essentially eliminated, within a given risk category, welds can be selected for examination based on additional factors such as the minimization of radiation exposure.(author).

  11. Structural condition assessment of in-service wood

    Science.gov (United States)

    Robert J. Ross; Brian K. Brashaw; Xiping Wang

    2006-01-01

    Wood is used extensively for both interior and exterior applications in the construction of a variety of structures (residential, agricultural, commercial, government, religious). The deterioration of an in-service wood member may result from a variety of causes during the life of a structure. It is important, therefore, to periodically assess the condition of wood...

  12. Status of the inservice inspection in codes; Stand der wiederkehrenden Pruefung im Regelwerk

    Energy Technology Data Exchange (ETDEWEB)

    Hienstorfer, W G [TUEV Energie- und Systemtechnik GmbH Baden-Wuerttemberg, Filderstadt (Germany); Hansch, M [Preussische Elektrizitaets-AG (Preussenelektra), Hannover (Germany); Koenig, G [Gemeinschaftskernkraftwerk Neckar GmbH, Neckarwestheim (Germany); Bath, H R [Kerntechnischer Ausschuss (KTA), Salzgitter (Germany)

    1998-11-01

    The body of regulatory nuclear engineering and inspection codes and subordinate codes defines on the one hand the general framework conditions for determination of the scope of inservice inspections, and on the other hand, for some defined components, contains detailed provisions relating to the scope of inservice tests to be made. These provisions are based on operating experience and engineering analyses. In order to establish a basis for optimization, the codes have been reviewed for possible optimization potentials, including a comparative analysis of foreign regulatory codes and approaches and the German codes. The conclusion drawn was that there is room for optimization, which should be done taking into account the following aspects: 1. Instrumentation for inservice monitoring of the state variables of relevance to the integrity of the primary loops has to be adapted, requiring acquisition of data showing local loading conditions and specific risks. 2. Inservice examinations of components and pipework should be optimized on the basis of updated, real-status information, i.e. upon availability of latest data showing verified operational loads and stresses and degradation mechanisms and risks, inspection methods, scopes and intervals can be optimized taking into account manufacturing quality. (orig./CB) [Deutsch] In dem aus gesetzlichen und untergesetzlichen Regelungen bestehenden kerntechnischen Regelwerk werden einerseits allgemeine Randbedingungen fuer die Bestimmung des Umfangs wiederkehrender Pruefungen vorgegeben und andererseits fuer einige Komponenten konkrete Festlegungen zum Pruefumfang getroffen. Diesen Festlegungen zum Pruefumfang lagen Betriebserfahrungen und ingenieurmaessige Analysen zugrunde. Als Grundlage fuer eine Optimierung der bisherigen Pruefumfaenge wurden die diesbezueglichen Moeglichkeiten des deutschen Regelwerks untersucht und ein Vergleich mit der Herangehensweise in den wichtigsten auslaendischen Regelwerken durchgefuehrt. Es zeigt

  13. Research and development on in-service inspection system for reactor vessel of FBR's

    International Nuclear Information System (INIS)

    Rindo, Hiroshi; Mitabe, Noriaki; Ara, Kuniaki; Nagai, Keiichi; Otaka, Masahiko

    1993-01-01

    In-Service Inspection (ISI) is required for main components and piping of FBRs. Visual test and volumetric examination of the reactor vessel (RV) from the outer surface are to be performed under severe conditions such as limited space, high temperature and high gamma dose rate during the reactor shutdown. Therefore, ISI should be performed by using a remote operation system, and the ISI system should be very compact. PNC has been developing the ISI system to apply to the RV inspection. Verification and performance tests of ISI system were carried out by use of the RV test model. This paper describes the system structure, system verification tests including operation and controlling the inspection robot, the functions of the visual test and the volumetric examination under the high temperature

  14. Review of P-scan computer-based ultrasonic inservice inspection system. Supplement 1

    International Nuclear Information System (INIS)

    Harris, R.V. Jr.; Angel, L.J.

    1995-12-01

    This Supplement reviews the P-scan system, a computer-based ultrasonic system used for inservice inspection of piping and other components in nuclear power plants. The Supplement was prepared using the methodology described in detail in Appendix A of NUREG/CR-5985, and is based on one month of using the system in a laboratory. This Supplement describes and characterizes: computer system, ultrasonic components, and mechanical components; scanning, detection, digitizing, imaging, data interpretation, operator interaction, data handling, and record-keeping. It includes a general description, a review checklist, and detailed results of all tests performed

  15. Specialists' meeting on in-service inspection and monitoring of LMFBRs. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-11-01

    The purpose of the meeting sponsored by the IAEA on the recommendation of the International Working Group on Fast Reactors (IWGFR) was attended by participants from France, the Federal Republic of Germany, Italy, Japan, the Netherlands, United Kingdom, United States of America, and two international organizations: CEC and IAEA. The purpose of the meeting was to review and discuss inspection requirements and concepts developed in the IWGFR member countries, development of inspection methods and their application in practical work and to recommend future development. The technical sessions were divided into four topical sessions as follows: General Concepts for In-Service Inspection of the Reactor Plant; Remotely Controlled Inspection Systems; Ultrasonic Test Methods; Miscellaneous Test Methods.

  16. Specialists' meeting on in-service inspection and monitoring of LMFBRs. Summary report

    International Nuclear Information System (INIS)

    1980-11-01

    The purpose of the meeting sponsored by the IAEA on the recommendation of the International Working Group on Fast Reactors (IWGFR) was attended by participants from France, the Federal Republic of Germany, Italy, Japan, the Netherlands, United Kingdom, United States of America, and two international organizations: CEC and IAEA. The purpose of the meeting was to review and discuss inspection requirements and concepts developed in the IWGFR member countries, development of inspection methods and their application in practical work and to recommend future development. The technical sessions were divided into four topical sessions as follows: General Concepts for In-Service Inspection of the Reactor Plant; Remotely Controlled Inspection Systems; Ultrasonic Test Methods; Miscellaneous Test Methods

  17. Foucault, Confucius and the In-Service Learning of Experienced Teachers in an Era of Managerialism

    Science.gov (United States)

    Huang, Hua

    2018-01-01

    By drawing on Foucault's theory of subjectification, this study presents a case study of two experienced teachers' in-service learning in the managerialist climate of Macau. The results indicate that the prevailing policies and administrative strategies on in-service learning served as the apparatus of managerialism working on teachers and…

  18. Knowledge and Beliefs about Developmental Dyslexia in Pre-Service and In-Service Spanish-Speaking Teachers

    Science.gov (United States)

    Soriano-Ferrer, Manuel; Echegaray-Bengoa, Joyce; Joshi, R. Malathesa

    2016-01-01

    The present study investigated knowledge, misconceptions, and lack of information about dyslexia among pre-service (PST) and in-service (IST) Spanish-speaking teachers in Spain and Peru. Two hundred and forty-six pre-service teachers and 267 in-service teachers completed the Knowledge and Beliefs about Developmental Dyslexia Scale (KBDDS).…

  19. Virtual in-service training from the librarians' point of view in libraries of medical sciences universities in Tehran

    Science.gov (United States)

    Mohaghegh, Niloofar; Raiesi Dehkordi, Puran; Alibeik, MohammadReza; Ghashghaee, Ahmad; Janbozorgi, Mojgan

    2016-01-01

    Background: In-service training courses are one of the most available programs that are used to improve the quantity and quality level of the staff services in various organizations, including libraries and information centers. With the advent of new technologies in the field of education, the problems and shortcomings of traditional in-service training courses were replaced with virtual ones. This study aimed to evaluate the virtual in-service training courses from the librarians' point of view in libraries of state universities of medical sciences in Tehran. Methods: This was a descriptive- analytical study. The statistical population consisted of all librarians at libraries of universities of medical sciences in Tehran. Out of 103 librarians working in the libraries under the study, 93 (90%) participated in this study. Data were collected, using a questionnaire. Results: The results revealed that 94/6% of librarians were satisfied to participate in virtual in-service training courses. In this study, only 45 out of 93 participants said that the virtual in-service courses were held in their libraries. Of the participants, 75.6% were satisfied with the length of training courses, and one month seemed to be adequate time duration for the librarians to be more satisfied. The satisfaction level of the individuals who participated in in-service courses of the National Library was moderate to high. A total of 84.4% participants announced that the productivity level of the training courses was moderate to high. The most important problem with which the librarians were confronted in virtual in-service training was the "low speed of the internet and inadequate computer substructures". Conclusion: Effectiveness of in-service training courses from librarians’ point of view was at an optimal level in the studied libraries. PMID:28491833

  20. Virtual in-service training from the librarians' point of view in libraries of medical sciences universities in Tehran.

    Science.gov (United States)

    Mohaghegh, Niloofar; Raiesi Dehkordi, Puran; Alibeik, MohammadReza; Ghashghaee, Ahmad; Janbozorgi, Mojgan

    2016-01-01

    Background: In-service training courses are one of the most available programs that are used to improve the quantity and quality level of the staff services in various organizations, including libraries and information centers. With the advent of new technologies in the field of education, the problems and shortcomings of traditional in-service training courses were replaced with virtual ones. This study aimed to evaluate the virtual in-service training courses from the librarians' point of view in libraries of state universities of medical sciences in Tehran. Methods: This was a descriptive- analytical study. The statistical population consisted of all librarians at libraries of universities of medical sciences in Tehran. Out of 103 librarians working in the libraries under the study, 93 (90%) participated in this study. Data were collected, using a questionnaire. Results: The results revealed that 94/6% of librarians were satisfied to participate in virtual in-service training courses. In this study, only 45 out of 93 participants said that the virtual in-service courses were held in their libraries. Of the participants, 75.6% were satisfied with the length of training courses, and one month seemed to be adequate time duration for the librarians to be more satisfied. The satisfaction level of the individuals who participated in in-service courses of the National Library was moderate to high. A total of 84.4% participants announced that the productivity level of the training courses was moderate to high. The most important problem with which the librarians were confronted in virtual in-service training was the "low speed of the internet and inadequate computer substructures". Conclusion: Effectiveness of in-service training courses from librarians' point of view was at an optimal level in the studied libraries.

  1. Surveying In-Service Teachers' Beliefs about Game-Based Learning and Perceptions of Technological Pedagogical and Content Knowledge of Games

    Science.gov (United States)

    Hsu, Chung-Yuan; Tsai, Meng-Jung; Chang, Yu-Hsuan; Liang, Jyh-Chong

    2017-01-01

    Using the Game-based-learning Teaching Belief Scale (GTBS) and the Technological Pedagogical Content Knowledge--Games questionnaire (TPACK-G), this study investigated 316 Taiwanese in-service teachers' teaching beliefs about game-based learning and their perceptions of game-based pedagogical content knowledge (GPCK). Both t-tests and ANOVA…

  2. Planning and programming of pre-operational and in-service inspections

    International Nuclear Information System (INIS)

    Udaondo, M.S.

    1984-01-01

    After a brief mention of the actual scope of in-service inspection work, conclusions are presented that relate to the preparations for inspections, making use of experience acquired since 1972 at 11 nuclear power plants in Spain which have commissioned such studies from one particular organization, and analyses are given of the advantages to be gained therefrom. Three different aspects of preparations for inspections are considered: (a) man-hour estimates and the duration of in-service inspections; (b) the sequence of action during a pre-operational inspection (assuming a typical functional organization) from definition of the codes of practice and standards applicable up to the issue of the final report and the schedule for distribution of the annual work load to be invested in a typical project, as a result of combining the two previous estimates, and (c) the documentary aspect of preparations for an inspection during a scheduled outage, as related to the various documents to be drawn up and their contents. Reference is made to the general training to be given to the staff in charge of inspection activities so as to provide them with information on, and a perspective of, the in-service inspection jobs required. (author)

  3. GIS In-Service Teacher Training Based on TPACK

    Science.gov (United States)

    Hong, Jung Eun; Stonier, Francis

    2015-01-01

    This article introduces the geographic information systems (GIS) in-service teacher training, focusing on the intersection of technological, pedagogical, and content knowledge (TPACK) for successful implementation of GIS in the classroom. Eleven social studies teachers in Georgia learned GIS technologies, inquiry-based learning, and social studies…

  4. Study and discussion on management of nuclear island in-service inspection procedure system in nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Xueliang; Fan Yancheng

    2014-01-01

    In-service inspection of nuclear island is the important way for keeping safety operation of nuclear power plant. Taking Daya Bay Nuclear Power Plant as example, the management problems of in-service inspection system was studied and discussed from the angle of references, contents, classifications etc. Based on comparison with French practice, some points of view on perfection of in-service inspection system and improvement of management ability under future multi-bases and multi-units management mode were presented. (authors)

  5. Qualification of NDT systems for in-service inspections of nuclear power plant pressure vessels

    International Nuclear Information System (INIS)

    Elfving, K.

    1998-11-01

    The goal of this study is to determine the requirements of the in-service inspection qualification in Europe, their feasibility in practice and to find out possible manufacture defects in test pieces used in practical trials. The literature study consists of qualification requirements set by European regulatory bodies and by the European nuclear power utilities. Also a brief summary of qualification requirements set by ASME Code, Section XI and comparison between ASME and European qualification requirements is included

  6. Selection of procedures for inservice inspections; Auswahl der Verfahren fuer wiederkehrende Pruefungen

    Energy Technology Data Exchange (ETDEWEB)

    Brast, G [Preussische Elektrizitaets-AG (Preussenelektra), Hannover (Germany); Britz, A [Bayernwerk AG, Muenchen (Germany); Maier, H J [Stuttgart Univ. (Germany). Staatliche Materialpruefungsanstalt; Seidenkranz, T [TUEV Energie- und Systemtechnik GmbH, Mannheim (Germany)

    1998-11-01

    At present, selection of procedures for inservice inspection has to take into account the legal basis, i.e. the existing regulatory codes, and the practical aspects, i.e. experience and information obtained by the general, initial inservice inspection or performance data obtained by the latest, recurrent inspection. However, regulatory codes are being reviewed to a certain extent in order to permit integration of technological progress. Depending on the degree of availability in future, of inspection task-specific, sensitive and qualified NDE techniques for inservice inspections (`risk based ISI`), the framework of defined inspection intervals, sites, and detection limits will be broken up and altered in response to progress made. This opens up new opportunities for an optimization of inservice inspections for proof of component integrity. (orig./CB) [Deutsch] Zur Zeit muss sich die Auswahl der Pruefverfahren an den gueltigen Regelwerken und, da es sich um wiederkehrende Pruefungen handelt, an der Basispruefung bzw. der letzten wiederkehrenden Pruefung orientieren. Jedoch vollzieht sich zur Zeit eine Oeffnung der Regelwerke, mit der man auch der Weiterentwicklung der Prueftechniken Rechnung traegt. In dem Masse, wie zukuenftig auf die Pruefaufgabe/Pruefaussage optimal abgestimmte und qualifizierte Prueftechniken mit einer hohen Nachweisempfindlichkeit am Bauteil fuer zielgerichtete wiederkehrende Pruefungen (als `risk based ISI`) zur Verfuegung stehen, wird der Rahmen mit festgelegten Pruefintervallen, Prueforten und festen Registriergrenzen gesprengt und variabel gestaltet werden koennen. Damit ergeben sich neue Moeglichkeiten fuer eine Optimierung der WKP zum Nachweis der Integritaet des Bauteils. (orig./MM)

  7. Improved in-service inspection program for management of degradation in steam generator tubing

    International Nuclear Information System (INIS)

    Kurtz, R.; Heasler, P.; Muscara, J.

    1992-01-01

    This paper presents an overview of significant results from NRC-sponsored research on steam generator tube integrity and inspection. Burst test results are described along with empirical models to relate flaw geometry and size to tube burst pressure. Results of round robin examinations of a retired-from-service steam generator to determine eddy current inspection reliability are presented. An evaluation and comparison of various sampling plans for in-service inspection of steam generators is discussed. Finally, performance demonstration qualification efforts for eddy current inspection systems are described

  8. Secondary Physics, Chemistry, and Biology (PCB Teachers’ Views about In-service Training Related to Curricular Change

    Directory of Open Access Journals (Sweden)

    Fatih Çağlayan Mercan

    2015-04-01

    Full Text Available In Turkey the Physics, Chemistry and Biology (PCB curricula were renewed in 2008. However, little in-service training for teachers has been conducted to disseminate the ideas in the new curricula. The purpose of this study was to investigate PCB teachers’ views on in-service training, which may serve as the base knowledge of educational change in Turkey that can be used in further curricular development. In Istanbul 99 teachers voluntarily participated in this qualitative case study. Data were collected utilizing semi-structured interviews and analyzed by employing constant comparative analysis. The data showed that for 40% of the teachers the in-service training was insufficient: the new curricula were not introduced to them adequately. Only 7% of the teachers expressed positive views towards the in-service training. The teachers were concerned about the incompetence of the trainers and the low quality of the training programs. 20% of the teachers felt that they need to keep up to date with the new curricula and establish ways of cooperation among teachers. The results imply that educational change is more than changing the curriculum, which requires serious planning for implementation requiring a reconceptualization of in-service training as part of a larger professional development framework.

  9. Sweet Rejuvenation: Linking In-Service and Teacher Induction.

    Science.gov (United States)

    McNair, Veda; And Others

    This paper describes a collaborative effort between a local education agency (LEA) and an institution of higher education to link inservice education with induction--teachers teaching teachers. The program, based on the Joyce coaching paradigm and recent cognitive development research, posits that long-term training conducted by trained teachers…

  10. Inservice Teacher Training: Experiencing German Culture Down Under

    Science.gov (United States)

    Jansen, Louise; Stracke, Elke

    2005-01-01

    In collaboration with the Australian Capital Territory (ACT) Department of Education and Training, the Australian National University has been offering a professional development program for language teachers (called LIFT, or Language Inservice for Teachers) for more than ten years. As the program is specially tailored to meet teachers' current…

  11. Becoming Reflective and Inquiring Teachers: Collaborative Action Research for In-service Chilean Teachers

    OpenAIRE

    Martine Pellerin; Fraño Ivo Paukner Nogués

    2015-01-01

    This article discusses the outcomes of a case study that engaged Chilean in-service teachers in systematic action research (AR) as a means of improving their pedagogical practice and effecting changes in their educational context. The study involved six in-service teachers from a region of Chile and two university researchers. The findings show that knowledge of systematic AR provided the teachers with the necessary means to engage in a critical reflection and inquiry process regarding their ...

  12. Risk-informed in-service inspections of nuclear power plants: European activities

    International Nuclear Information System (INIS)

    Simola, K.; Gandossi, L.

    2010-01-01

    Risk-informed in-service inspection (RI-ISI) methods aim at enhancing ISI effectiveness by taking into account the risk importance of possible inspection sites. These methods are widely applied in US, but in Europe the situation is different, as there are many regulatory environments implying a variety of ISI codes and standards and national guidelines. The objective of the European Network for Inspection Qualification, ENIQ, is to co-ordinate and to manage at European level expertise and resources for the qualification of non-destructive inspection techniques and procedures primarily for the in-service inspection of nuclear components. ENIQ has established a Task Group on Risk (TGR) to work towards developing best practice for RI-ISI methodologies. TGR has published a European framework document for risk-informed in-service inspection, and the group has been working at producing more detailed recommended practices and discussion documents on several RI-ISI related issues. In addition, TGR has been active in initiating international projects, such as the JRC-OECD/NEA coordinated RI-ISI benchmark exercise (RISMET). This paper describes the activities and publications of TGR to date, and summarises the contents and main results of the RISMET RI-ISI benchmark exercise. (orig.)

  13. Effect of electroslag remelting on carbides in 8Cr13MoV martensitic stainless steel

    Science.gov (United States)

    Zhu, Qin-tian; Li, Jing; Shi, Cheng-bin; Yu, Wen-tao

    2015-11-01

    The effect of electroslag remelting (ESR) on carbides in 8Cr13MoV martensitic stainless steel was experimentally studied. Phases precipitated from liquid steel during solidification were calculated using the Thermo-Calc software. The carbon segregation was analyzed by original position analysis (OPA), and the carbides were analyzed by optical microscopy (OM), scanning electron microscopy (SEM), energy- dispersive X-ray spectroscopy (EDS) and X-ray diffraction (XRD). The results indicated that more uniform carbon distribution and less segregation were obtained in the case of samples subjected to the ESR process. After ESR, the amount of netty carbides decreased significantly, and the chromium and vanadium contents in the grain-boundary carbides was reduced. The total area and average size of carbides were obviously smaller after the ESR process. In the sample subjected to ESR, the morphology of carbides changed from lamellar and angular to globular or lump, whereas the types of carbides did not change; both M23C6 and M7C3 were present before and after the ESR process.

  14. An in-service inspection method: the use of focused probes for the detection and sizing in DDT Plates 1 and 2

    International Nuclear Information System (INIS)

    Birac, A.M.; Pincemaille, G.; Saglio, R.; Cattiauz, G.; Morisseau, P.

    1983-01-01

    As part of the DDT programme to evaluate the nondestructive testing methods used during the in-service inspection (ISI) of PWR vessels, the UKAEA asked the CEA-STA-SCND to perform the ultrasonic examination of two test-plates. Each plate was bisected across its full width by a full-thickness butt-weld in which calibrated defects of various natures, dimensions, orientations have been inserted. It was required that the implementation of control, the equipment and the subsequent data analysis represent as nearly as possible the French procedure in force during the pre-service and in-service inspection of a PWR vessel. As suggested by the UKAEA, to evaluate the influence of examiners on the results, the examinations have been carried out twice by two independent teams: one from the CEA-STA-SCND and the second from INTERCONTROLE (a CEA subsidiary company). Procedure and results are given. (author)

  15. Supporting Elementary Education in-Service Teachers' Proficiency in Planning STEM-Centric Lessons

    Science.gov (United States)

    Bowers, Sharon W.

    The purpose of this study was to explore the McDaniel College Elementary STEM Instructional Leader (ESIL) pilot cohort's ability to proficiently plan lessons that incorporated the Maryland State STEM Standards of Practice (SOP), targeting integration of STEM content, inquiry learning, students' abilities to collaborate as a STEM team and students' strategic application of technology. Data collection, in the form of reviewing and analyzing study participants' lesson plans and self-reflections, was completed by three independent assessors. The researcher examined the interrater reliability among the three assessors using the Fleiss' kappa statistic. A 0.91 proportion of agreement consensus was documented among the three assessors. A test of hypothetical value was conducted using the nonparametric Wilcoxonsigned- rank Test. Interpretation of the Wilcoxon-signed-rank Test results suggest that the sample population demonstrated proficient planning abilities for the four targeted Maryland State STEM SOP. Findings from this research add to the field's knowledge of elements in the promotion of graduate coursework that leads to elementary in-service teachers' proficiency in planning STEM-centric lessons, however the findings also have broader implications for teacher education at large. The McDaniel College ESIL model could frame K-12 teacher education for both preservice and in-service teachers. The pragmatic, hybrid experience maximizes flexibility, promotes analytical thinking and self-reflection and builds communication skills. The introduction and development of inquiry and design-based learning through the 7E Learning Cycle develops the teachers' understanding of practices promoted not only within the Maryland State STEM SOP, but also within the Next Generation Science Standards. The McDaniel College ESIL model also builds upon the collective efforts of academia, a non-profit STEM research facility, and local school divisions to align efforts that may lead to

  16. In-service diagnostics of main circulating circuit pipes of WWER nuclear power plants

    International Nuclear Information System (INIS)

    Svoboda, V.; Merta, J.; Merta, V.

    1982-01-01

    The application is discussed of the acoustic emission method for testing the integrity of the components of the main circulating circuit of the WWER 440 nuclear power plant. A description is given of the main circulating circuit and a stress analysis on the basis of strength computations considering operating modes is presented. An analysis is also presented of the possible damage of the pipe material as related to the application of the acoustic emission method for in-service inspection of the pipes. Certain practical problems of application are discussed. (author)

  17. Interaction between periodic in-service inspection requirements and design

    International Nuclear Information System (INIS)

    Prot, A.C.; Saglio, R.

    1979-03-01

    After reviewing the requirements specific of periodic In-Service Inspection related to safety problems, especially for the pressure vessels, and taking into account the experience gained with several PWR reactors, the authors show these requirements could lead to modify the primary circuit design

  18. The Special Education Director's Role in Inservice Training Programs

    Science.gov (United States)

    Donatell, Henry

    1978-01-01

    Reviewed in the article on the special education director's role in inservice training programs are planning procedures (including evaluation of the present program by all staff), types of programs offered (such as summer curriculum writing and teacher orientation week), and evaluation methods. (CL)

  19. Influence of in-service degradation on strain localization in steel of main gas pipelines

    OpenAIRE

    Maruschak, Pavlo; Bishchak, Roman; Panin, Sergey Viktorovich; Pylypenko, Andriy; Menou, Abdellah; Danyliuk, Iryna

    2014-01-01

    General regularities in the failure kinetics of steel of main gas pipelines (17GS) are established using the method of complete stress-strain curves, meanwhile in-service degradation of metals is taken into account. The influence of material degradation on material properties under static tensioning is considered using two independent approaches: the phenomenological model of damage accumulation in metals, and the fractographic analysis method. The accumulation of in-service damage is found t...

  20. The Development and Evolution of an Introductory Statistics Course for In-Service Middle-Level Mathematics Teachers

    Science.gov (United States)

    Schmind, Kendra K.; Blankenship, Erin E.; Kerby. April T.; Green, Jennifer L.; Smith, Wendy M.

    2014-01-01

    The statistical preparation of in-service teachers, particularly middle school teachers, has been an area of concern for several years. This paper discusses the creation and delivery of an introductory statistics course as part of a master's degree program for in-service mathematics teachers. The initial course development took place before the…

  1. Australian Primary In-Service Teachers' Conceptions of Geography

    Science.gov (United States)

    Preston, Lou

    2015-01-01

    This paper reports on the second part of a two pronged qualitative investigation that examines the ways in which Australian primary teachers conceptualise geography and geography teaching. In the first part of the project, 47 pre-service primary teachers were surveyed. In this paper, I draw on interviews with six in-service primary teachers to…

  2. In-Service Education within Schools: A Comparative Perspective.

    Science.gov (United States)

    Dahawy, Bayoumi M.

    This paper prepared in the United States by a visiting faculty member of the Suez Canal University in Egypt, presents a comparative study that finds that school-based in-service training sessions, in which teachers learn within their own teaching environments, do much to encourage more teachers to adopt a more positive attitude to the…

  3. Examples of in-service inspections and typical maintenance schedule for low-power research reactors

    International Nuclear Information System (INIS)

    Boeck, H.

    1997-01-01

    In-service inspection methods for low-power research reactors are described which have been developed during the past 37 years of the operation of the TRIGA reactor Vienna. Special tools have been developed during this period and their application for maintenance and in-serve inspection is discussed. Two practical in-service inspections at a TRIGA reactor and at a MTR reactor are presented. Further a typical maintenance plan for a TRIGA reactor is listed in the annex. (author)

  4. Risk analysis of in-service pressure piping containing defects

    International Nuclear Information System (INIS)

    Lin, Y.C.; Xie, Y.J.; Wang, X.H.; Luo, H.

    2004-01-01

    The reliability of pressure piping containing defects is important in engineering. The failure probability of pressure piping containing defects may be used as a guide to the most economic deployment of resources on maintenance, inspection and repair. This paper presents a probabilistic assessment methodology for in-service pressure piping containing defects, which is especially designed for programming. It is based on three assessment codes, BS 7910, R6 and SAPV-99, considering uncertainties in operating loadings, flaw sizes, material fracture toughness and flow stress. A general sampling computation method of stress intensity factor (SIF), in the form of the relationship between SIF and axial force and bending moment and torsion, is adopted. This relationship has been successfully used in developing software, Safety Assessment System of In-service Pressure Piping Containing Flaws (SAPP-2003), to assess planar and non-planar flaws. A numerical example is presented to illustrate the application of SAPP-2003 for calculating the failure probabilities of separate defects and for the assessed pressure piping

  5. NRC inspections of licensee activities to improve the performance of motor-operated valves

    International Nuclear Information System (INIS)

    Scarbrough, T.G.

    1992-01-01

    The NRC regulations require that components important to the safe operation of a nuclear power plant be treated in a manner that provides assurance of their proper performance. Despite these regulatory requirements, operating experience and research programs have raised concerns regarding the performance of motor-operated valves (MOVs) in nuclear power plants. In June 1990, the staff issued NUREG-1352, Action Plans for Motor-Operated Valves and Check Valves, which contains planned actions to organize the activities aimed at resolving the concerns about MOV performance. A significant task of the MOV action plan is the staff's review of the implementation of Generic Letter (GL) 89-10 (June 28, 1989), 'Safety-Related Motor-Operated Valve Testing and Surveillance,' and its supplements, by nuclear power plant licensees. The NRC staff has issued several supplements to GL 89-10 to provide additional guidance for use by licensees in responding to the generic letter. The NRC staff has conducted initial inspections of the GL 89-10 programs at most licensee facilities. This paper outlines some of the more significant findings of those inspections. For example, licensees who have begun differential pressure and flow testing have found some MOVs to require more thrust to operate than predicted by the standard industry equation with typical valve factors assumed in the past. The NRC staff has found weaknesses in licensee procedures for conducting the differential pressure and flow tests, the acceptance criteria for the tests in evaluating the capability of the MOV to perform its safety function under design basis conditions, and feedback of the test results into the methodology used by the licensee in predicting the thrust requirements for other MOVs. Some licensees have not made adequate progress toward resolving the MOV issue for their facilities within the recommended schedule of GL 89-10

  6. A Practice onto Personnel In-Service Training’s Affect to Job Satisfaction

    Directory of Open Access Journals (Sweden)

    Emrah Köksal

    2011-06-01

    Full Text Available The kitchen which is qualified as the hearth of hotels is a department includes kitchen staff whose responsibilities, authority and duties are identified related to an organizational structure and in a hierarchy instead of being merely a physical space with equipment and working areas that are built for food production. The aim of kitchen is to realize food production in the limits of cost, quality and hygiene standards of hotel. Beside many factors which affect job satisfaction and organizational loyalty the training which is going to be received is also important. As knowing the job increases the job satisfaction and self confidence and it also affects the organizational loyalty in a positive way. This study aims that grups hotel, how does in-service training affect kitchen personnel. In this study applied filed technique used in and firstly searched the factors affect job satisfaction and thoughts about in-service training then applied an one-week training to the same personnel. A different survey performed order to measure the affect to job satisfaction of personnel who was in training and to determine is the in-service training suitable.

  7. Spanish guideline for the definition and assessment of risk-informed inservice inspection programs for piping

    International Nuclear Information System (INIS)

    Figueras, J.M.; Olivar, F.; Mendoza, C.; Vazquez, T.; Morales, L.; Bros, J.; Mach, I.; Gutierrez, E.

    2001-01-01

    The recent emphasis on risk-informed in-service inspection has been taken on by the Spanish Utilities and the Spanish Regulatory Body in their proposal for a co-operation project for defining a Risk-Informed In-Service Inspection Guideline for Piping. This paper describes first the main features of this Spanish guideline and then the results of the pilot applications developed in order to check the consistency of the guideline. (authors)

  8. Spanish guideline for the definition and assessment of risk-informed inservice inspection programs for piping

    Energy Technology Data Exchange (ETDEWEB)

    Figueras, J.M.; Olivar, F.; Mendoza, C.; Vazquez, T. [CSN, Madrid (Spain); Morales, L. [UNESA, Madrid (Spain); Bros, J.; Mach, I. [Tecnatom, Madrid (Spain); Gutierrez, E. [Iberinco, Madrid (Spain)

    2001-07-01

    The recent emphasis on risk-informed in-service inspection has been taken on by the Spanish Utilities and the Spanish Regulatory Body in their proposal for a co-operation project for defining a Risk-Informed In-Service Inspection Guideline for Piping. This paper describes first the main features of this Spanish guideline and then the results of the pilot applications developed in order to check the consistency of the guideline. (authors)

  9. Using the Computer in Special Vocational Programs. Inservice Activities.

    Science.gov (United States)

    Lane, Kenneth; Ward, Raymond

    This inservice manual is intended to assist vocational education teachers in using the techniques of computer-assisted instruction in special vocational education programs. Addressed in the individual units are the following topics: the basic principles of computer-assisted instruction (TRS-80 computers and typing on a computer keyboard); money…

  10. Component unavailability versus inservice test (IST) interval: Evaluations of component aging effects with applications to check valves

    International Nuclear Information System (INIS)

    Vesely, W.E.; Poole, A.B.

    1997-07-01

    Methods are presented for calculating component unavailabilities when inservice test (IST) intervals are changed and when component aging is explicitly included. The methods extend usual approaches for calculating unavailability and risk effects of changing IST intervals which utilize Probabilistic Risk Assessment (PRA) methods that do not explicitly include component aging. Different IST characteristics are handled including ISTs which are followed by corrective maintenances which completely renew or partially renew the component. ISTs which are not followed by maintenance activities needed to renew the component are also handled. Any downtime associated with IST, including the test downtime and the following maintenance downtime, is included in the unavailability evaluations. A range of component aging behaviors is studied including both linear and nonlinear aging behaviors. Based upon evaluations completed to date, pooled failure data on check valves show relatively small aging (e.g., less than 7% per year). However, data from some plant systems could be evidence for larger aging rates occurring in time periods less than 5 years. The methods are utilized in this report to carry out a range of sensitivity evaluations to evaluate aging effects for different possible applications. Based on the sensitivity evaluations, summary tables are constructed showing how optimal IST interval ranges for check valves can vary relative to different aging behaviors which might exist. The evaluations are also used to identify IST intervals for check valves which are robust to component aging effects. General insights on aging effects are also extracted. These sensitivity studies and extracted results provide useful information which can be supplemented or be updated with plant specific information. The models and results can also be input to PRAs to determine associated risk implications

  11. Nondestructive examination (NDE) Reliability for Inservice Inspection of Light Water Reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Good, M.S.; Heasler, P.G.; Hockey, R.L.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V.

    1992-07-01

    The Evaluation and Improvement of NDE reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to the Regulatory and ASME Code requirements, based on material properties, service conditions, and NDE uncertainties

  12. Becoming Reflective and Inquiring Teachers: Collaborative Action Research for In-service Chilean Teachers

    Directory of Open Access Journals (Sweden)

    Martine Pellerin

    2015-08-01

    Full Text Available This article discusses the outcomes of a case study that engaged Chilean in-service teachers in systematic action research (AR as a means of improving their pedagogical practice and effecting changes in their educational context. The study involved six in-service teachers from a region of Chile and two university researchers. The findings show that knowledge of systematic AR provided the teachers with the necessary means to engage in a critical reflection and inquiry process regarding their own practice. The teacher participants also perceived the self-reflective spiral of reflection and action to be crucial in establishing new habits of inquiry and reflection about their own pedagogical actions. The findings support earlier studies (e.g., Price & Valli, 2005; Steven & Kitchen, 2005, 2011 concerning the necessity of including knowledge of systematic AR in teacher preparation programs in order to foster strong habits of inquiry and reflection among preservice teachers. Finally, the study suggests that participation in a systematic reflection and inquiry process contributes to empowering in-service teachers to become agents of pedagogical change through their own actions.

  13. Perceived Quality of In-Service Communication and Counseling Among Adolescents Undergoing Voluntary Medical Male Circumcision.

    Science.gov (United States)

    Van Lith, Lynn M; Mallalieu, Elizabeth C; Patel, Eshan U; Dam, Kim H; Kaufman, Michelle R; Hatzold, Karin; Marcell, Arik V; Mavhu, Webster; Kahabuka, Catherine; Mahlasela, Lusanda; Njeuhmeli, Emmanuel; Seifert Ahanda, Kim; Ncube, Getrude; Lija, Gissenge; Bonnecwe, Collen; Tobian, Aaron A R

    2018-04-03

    Experience with providers shapes the quality of adolescent health services, including voluntary medical male circumcision (VMMC). This study examined the perceived quality of in-service communication and counseling during adolescent VMMC services. A postprocedure quantitative survey measuring overall satisfaction, comfort, perceived quality of in-service communication and counseling, and perceived quality of facility-level factors was administered across 14 VMMC sites in South Africa, Tanzania, and Zimbabwe. Participants were adolescent male clients aged 10-14 years (n = 836) and 15-19 years (n = 457) and completed the survey 7 to 10 days following VMMC. Adjusted prevalence ratios (aPRs) were estimated by multivariable modified Poisson regression with generalized estimating equations and robust variance estimation to account for site-level clustering. Of 10- to 14-year-olds and 15- to 19-year-olds, 97.7% and 98.7%, respectively, reported they were either satisfied or very satisfied with their VMMC counseling experience. Most were also very likely or somewhat likely (93.6% of 10- to 14-year olds and 94.7% of 15- to 19-year olds) to recommend VMMC to their peers. On a 9-point scale, the median perceived quality of in-service (counselor) communication was 9 (interquartile range [IQR], 8-9) among 15- to 19-year-olds and 8 (IQR, 7-9) among 10- to 14-year-olds. The 10- to 14-year-olds were more likely than 15- to 19-year-olds to perceive a lower quality of in-service (counselor) communication (score quality of in-service communication as high and recommend VMMC to their peers; however, many adolescents desire more discussion about key topics outlined in World Health Organization guidance.

  14. Automation of eddy current system for in-service inspection of turbine and generator rotor bores

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The current project (EPRI-RP-1975-5) is a continuation of activities that began several years ago. Those results (EPRI-RP-1957-1) indicated that eddy current testing shows promise for in-service inspection. The current project investigates the degree to which eddy current testing can be used to replace bore magnetic particle testing. For this purpose, correlation studies between eddy current and magnetic particle tests are being undertaken on laboratory rotor sections and field test pieces of rotors. The eddy current data are to be gathered automatically by a combination of the Nortec-25L Eddyscope (to provide the analog eddy current signals) and the General Electric DATAQ/sup TM/ (a registered trademark of the General Electric Co.) System (to perform the automatic data acquisition). This paper describes some test results on a flaked laboratory rotor section

  15. Development and Evaluation of the Efficiency of In-Service Training Program with the Theme of Peace Education

    Science.gov (United States)

    Basaran, Semra Demir; Karakurt, Sevgi Özden

    2017-01-01

    In this article, an in-service training program was developed and evaluated to improve the peace education competencies of primary school teachers. This program, named as In-Service Training Program with the Theme of Peace Education for Primary Teachers (BEHEP), was based on the system approach. The implementation was completed in 28 hours with…

  16. A risk-informed approach to optimising in-service inspection of piping

    International Nuclear Information System (INIS)

    Billington, A.; Monette, P.

    1999-01-01

    Traditional criteria for the selection of in-service inspection locations in piping, have come to be regarded as being out-of-touch with current knowledge of piping failures and with current measures of safety importance. An alternative , risk-informed, method has been developed and successfully licensed, that systematically establishes an inspection plan addressing all safety-related piping systems, in a way that is optimized with respect to the safety gain achieved through in-service inspection. The principles of the method are discussed and the results of several applications are summarized, all of which demonstrate that the risk-informed program would lead to significant improvements in the overall level of plant safety, while at the same time re-distributing the inspections in such a way that reduces both plant costs and radiation exposure to personnel.(author)

  17. Consensus structures of the Mo(v) sites of sulfite-oxidizing enzymes derived from variable frequency pulsed EPR spectroscopy, isotopic labelling and DFT calculations.

    Science.gov (United States)

    Enemark, John H

    2017-10-10

    Sulfite-oxidizing enzymes from eukaryotes and prokaryotes have five-coordinate distorted square-pyramidal coordination about the molybdenum atom. The paramagnetic Mo(v) state is easily generated, and over the years four distinct CW EPR spectra have been identified, depending upon enzyme source and the reaction conditions, namely high and low pH (hpH and lpH), phosphate inhibited (P i ) and sulfite (or blocked). Extensive studies of these paramagnetic forms of sulfite-oxidizing enzymes using variable frequency pulsed electron spin echo (ESE) spectroscopy, isotopic labeling and density functional theory (DFT) calculations have led to the consensus structures that are described here. Errors in some of the previously proposed structures are corrected.

  18. When school-based, in-service teacher training sharpens pedagogical awareness

    DEFF Research Database (Denmark)

    Lund, Lea

    2018-01-01

    Research in the field of professional development (PD) stresses the importance of the development of professional learning communities (PLCs) designed to promote the process of inquiry in teaching. PLCs are of great importance with regard to both school improvement and in-service teacher training...

  19. Surveillance and in-service inspection (SISI) program at FFTF

    International Nuclear Information System (INIS)

    Conrads, T.J.

    1980-01-01

    Assurance of the integrity of the sodium coolant pressure boundaries of the Fast Flux Test Facility systems and components is essential for safe operation. A program has been developed to monitor the integrity of the coolant boundaries and certain plant conditions. Specific equipment and features have been designed into the plant for monitoring. The purpose of SISI is to prevent failures or minimize their consequences through early detection. The program which administers the requirements for monitoring applicable plant conditions whose integrity is necessary to protect public health and safety is known as the Surveillance and In-service Inspection (SISI) Program. The SISI program utilizes a wide range of monitoring techniques to ensure that material degradation or structural deficiencies will not result in the loss of the ability to shut down the reactor, cool the reactor core, or cause the release of radioactive material to the environment

  20. Flexibility-based damage detection for in-service highway bridge

    Science.gov (United States)

    Dahal, Sushil; Jang, Shinae; Mensah-Bonsu, Priscilla

    2012-04-01

    Highway bridges are the backbones of a country's road network infrastructure. In order to efficiently maintain these important structures, structural health monitoring (SHM) can be implemented to impart a more deterministic management procedure. To date, many damage detection strategies have been developed and implemented on lab-scale or simple bridge structures however, damage detection research has rarely been conducted taking full scale in-service structures into account with ambient vibration. Among the different approaches modal flexibility method is one of the sensitive tools for damage detection which has been widely used over the last two decades. This paper presents a damage detection based on the stochastic damage locating vector (SDLV) method for an in-service highway bridge using ambient vibration data from long-term SHM. The target bridge was equipped with a long-term SHM system as a part of a research project of the University of Connecticut. The ambient vibration data during 2001 and 2005 are used to identify the damage on the highway bridge. Finally, the potential damage locations are determined using the SDLV method with the limited number of sensors.

  1. Cuatro Modelos para Disenar Actividades de Capacitacion de Docentes (Four Models to Design In-Service Teacher Training Activities).

    Science.gov (United States)

    Valle, Victor M.

    In designing inservice teacher training activities, it is necessary to apply educational principles and teaching and learning techniques which are suitable for adult education programs. Four models for designing inservice teacher training programs are the Malcom Knowles Model, the Leonard Nadler Model, the Cyril O. Houle Model, and the William R.…

  2. In-service inspection in the Superphenix 1 vessels interspace

    International Nuclear Information System (INIS)

    Asty, M.; Saglio, R.

    1983-03-01

    The design of Superphenix 1 reactor vessels allows their in-service inspection. A self-propelling engine, the MIR, has been concieved for this need: it can do a visual and ultrasonic inspection. The MIR can move in the whole vessels interspace. The operating conditions are specified and the principle characteristics of the MIR engine are presented [fr

  3. Evaluation and improvement in nondestructive examination (NDE) reliability for inservice inspection of light water reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Andersen, E.S.; Bowey, R.E.; Diaz, A.A.; Good, M.S.; Heasler, P.G.; Hockey, R.L.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V.

    1991-01-01

    This program is intended to establish the effectiveness, reliability and adequacy of inservice inspection of reactor pressure vessels and primary piping systems and the impact of ISI reliability on system integrity. The objectives of the program include: (a) determine the effectiveness and reliability of ultrasonic inservice inspection (ISI) performed on commercial, light water reactor pressure vessels and piping; (b) recommend Code changes to the inspection procedures to improve the reliability of ISI; (c) using fracture mechanics analysis, determine the impact of NDE unreliability on system safety and determine the level of inspection reliability required to assure a suitably low failure probability; (d) evaluate the degree of reliability improvement which could be achieved using improved NDE techniques; and (e) based on importance of component to safety, material properties, service conditions, and NDE uncertainties, formulate improved inservice inspection criteria (including sampling plan, frequency, and reliability of inspection) for revisions to ASME Section XI and regulatory requirements needed to assure suitably low failure probabilities

  4. Examination of in-service risk management at the level of the draft project for Cigeo

    International Nuclear Information System (INIS)

    2014-01-01

    This document reports the opinion of the IRSN on the issue of in-service risk management as it appears in the draft project of Cigeo. After having recalled the general context of the ASN request for this opinion, and presented the ANDRA file on in-service risk-management of the draft project for Cigeo, this report describes the underground installation and the different flows during the exploitation phase, and recalls the various evolutions of Cigeo general design from the 2009 file to the draft project. The next part reports the examination by the IRSN of the relevance of the in-service safety approach by the ANDRA. The next chapter reports the examination of the risk analysis made by the ANDRA on radioactive material dissemination, fire (protection measures, ventilation control, case of exothermal reactions), explosion, handling, co-activity, as well as ageing and maintenance of storage components, intervention in accidental and incidental situation and possibility of retrieval of waste packages

  5. Development and validation of real-time SAFT-UT system for inservice inspection of LWRs

    International Nuclear Information System (INIS)

    Doctor, S.R.; Hall, T.E.; Reid, L.D.; Mart, G.A.

    1988-01-01

    The Pacific Northwest Laboratory is working to design, fabricate, and evaluate a real-time flaw detection and characterization system based on the synthetic aperture focusing technique for ultrasonic testing (SAFT-UT). The system is designed to perform inservice inspection of light-water reactor components. Included objectives of this program for the Nuclear Regulatory Commission are to develop procedures for system calibration and field operation, to validate the system through laboratory and field inspections, and to generate an engineering database to support ASME Code acceptance of the technology. This progress report covers the programmatic work from October 1986 through September 1987. (author)

  6. From laboratory corrosion tests to a corrosion lifetime for wood fasteners : progress and challenges

    Science.gov (United States)

    Samuel L. Zelinka; Dominique Derome; Samuel V. Glass

    2010-01-01

    Determining a “corrosion-lifetime” for fasteners embedded in wood treated with recently adopted preservative systems depends upon successfully relating results of laboratory tests to in-service conditions. In contrast to laboratory tests where metal is embedded in wood at constant temperature and moisture content, the in-service temperature and moisture content of wood...

  7. IAEA-RCA training course on in-service inspection of research reactors

    International Nuclear Information System (INIS)

    2002-01-01

    Bhabha Atomic Research Centre (BARC) has acquired a wide range of experience for over four decades in design, construction, operation and maintenance of research reactors. The two-week training course on In-Service Inspection of Research Reactors (ISI) has greatly increased the awareness in the field of ISI of Research Reactors. The training course has been formulated so as to cover most of the topics relevant to ISI of research reactors. Important topics such as rationale for in-service inspection, material degradation mechanisms, non-destructive examination techniques, design evaluation of flaws and radiological, codal and regulatory aspects of ISI for research reactors were covered. Lectures on ISI of elastomeric materials and concrete structures, which are generally used in the construction of reactors have also been included in the course. Papers relevant to INIS are indexed separately

  8. In-Service Aircraft Transmission Life Modeling for Improved Flight Safety, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — It is proposed to develop an accurate, in-service transmission life-estimation system for the prediction of remaining component and system life for a helicopter...

  9. Constructivism and the use of performance assessment in science: A comparative study of beliefs among preservice and inservice teachers

    Science.gov (United States)

    Bednarski, Marsha H.

    Reform efforts in science education stress the importance of preservice and inservice teacher education in curriculum, instruction, and assessment. A change in current student assessment practices is seen as the catalyst in the reform of curriculum and instruction. Recommended for assessment of the proposed inquiry-based science programs are performance-based assessments (National Research Council, 1996). The constructivist philosophy, the foundation for these reform efforts, proposes that knowledge acquisition by the learner is a result of the interaction between what is brought to the learning situation and what is experienced while in it. Literature supports the use of constructivist-based instructional strategies for preservice and inservice teacher education (American Federation of Teachers, National Council on Measurement in Education, and National Education Association, 1990). Literature also provides support for the importance of teacher beliefs in relation to the successful transfer of these instructional strategies (Keegan, 1992; Nespor, 1987). There is not supporting evidence related to constructivist instructional strategies and teacher beliefs transferring to the use of performance assessment. This study identified whether preservice and inservice teachers differed with respect to their beliefs about constructivist-based learning strategies and performance assessment. It also identified whether teacher beliefs held about constructivist-based learning strategies were related to the construction of assessments they developed for use in their classrooms. Education majors enrolled in a Northeastern university's assessment course and inservice teachers from three Northeast public school districts participated in this study. Results of a 36-item belief survey, administered to preservice and inservice teachers, and a 10-item checklist, used to score assessment examples provided by the teachers, concluded that attitudes toward constructivist-based learning

  10. Preservice to Inservice: Does Mathematics Anxiety Change with Teaching Experience?

    Science.gov (United States)

    Gresham, Gina

    2018-01-01

    Inservice teachers, participants in a prior study on mathematics anxiety, were revisited to determine whether their levels of mathematics anxiety still existed and/or continued to change after 5 years teaching experience. A 98-item Likert-type survey, informal discussions, informal interviews, and questionnaire-guided narrative interviews were…

  11. Impact of In-Service Training and Staff Development on Workers' Job Performance and Optimal Productivity in Public Secondary Schools in Osun State, Nigeria

    Science.gov (United States)

    Fejoh, Johnson; Faniran, Victoria Loveth

    2016-01-01

    This study investigated the impact of in-service training and staff development on workers' job performance and optimal productivity in public secondary schools in Osun State, Nigeria. The study used the ex-post-facto research design. Three research questions and three hypotheses were generated and tested using questionnaire items adapted from…

  12. In-Service Aircraft Transmission Life Modeling for Improved Flight Safety, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — It is proposed to develop an accurate, in-service transmission life-use estimation system for the prediction of remaining component and system life for a helicopter...

  13. An Investigation on the impact of using problem-based trainings in the in-service courses on the teachers' performance and capabilities, by relying on the elementary sixth grade mathematics book (case study: the city of Ahvaz

    Directory of Open Access Journals (Sweden)

    Pari Cheraq

    2017-02-01

    Full Text Available Changes in the administrative structure of the education system and the need to coordinate with the world of science and technology and hence, the need to update the general and technical information and knowledge, have doubled the importance and necessity of holding the new and efficient in-service trainings for the teachers. In this study, the attempt was taken to examine and analyze the impact of using problem-based trainings during the in-service courses on the teachers' performance and capabilities, by relying on the mathematics book of the sixth grade elementary level (case study: the city of Ahvaz. To do so, using a quasi-experimental study, 37 teachers of the sixth grade were selected from the elementary schools of Ahvaz city. For the in-service training courses on the teaching of mathematics, the problem-based learning method was used. After conducting the problem-based teaching method and the traditional method of teaching, through using the test and the standard questionnaire, the data about the teaching practice and the capabilities of the teachers were collected. Using t-test for the paired and independent samples, it was demonstrated that the problem-based in-service trainings, enhance the teachers' capabilities and performance regarding the problem-solving skills.

  14. Evaluation of a statewide science inservice and outreach program: Teacher and student outcomes

    Science.gov (United States)

    Lott, Kimberly Hardiman

    Alabama Science in Motion (ASIM) is a statewide in-service and outreach program designed to provide in-service training for teachers in technology and content knowledge. ASIM is also designed to increase student interest in science and future science careers. The goals of ASIM include: to complement, enhance and facilitate implementation of the Alabama Course of Study: Science, to increase student interest in science and scientific careers, and to provide high school science teachers with curriculum development and staff development opportunities that will enhance their subject-content expertise, technology background, and instructional skills. This study was conducted to evaluate the goals and other measurable outcomes of the chemistry component of ASIM. Data were collected from 19 chemistry teachers and 182 students that participated in ASIM and 6 chemistry teachers and 42 students that do not participate in ASIM using both surveys and student records. Pre-treatment Chi-Square tests revealed that the teachers did not differ in years of chemistry teaching experience, major in college, and number of classes other than chemistry taught. Pre-treatment Chi-Square tests revealed that the students did not differ in age, ethnicity, school classification, or school type. The teacher survey used measured attitudes towards inquiry-based teaching, frequency of technology used by teacher self-report and perceived teaching ability of chemistry topics from the Alabama Course of Study-Science. The student surveys used were the Test of Science Related Attitudes (TOSRA) and a modified version of the Test of Integrated Process Skills (TIPS). The students' science scores from the Stanford Achievement Test (SAT-9) were also obtained from student records. Analysis of teacher data using a MANOVA design revealed that participation in ASIM had a significantly positive effect on teacher attitude towards inquiry-based teaching and the frequency of technology used; however, there was no

  15. Development of Surveillance and In-Service Inspection Programme for Indian Research Reactors Cirus and Dhruva

    International Nuclear Information System (INIS)

    Shukla, D.K.

    2006-01-01

    Many safety requirements for research reactors are quite similar to those of power reactors. For research reactors with a higher hazard potential, the use of safety codes and guides for power reactors is more appropriate. However, there are many important differences between power reactors and research reactors that must be taken into account to ensure that adequate safety margins are available in design and operation of the research reactor. Most research reactors may have small potential for hazard to the public compared to power reactors but may pose a greater potential hazard to the plant operators. The need for greater flexibility in use of research reactors for individual experiments requires a different safety approach. Safety rules for power reactors are required to be substantially modified for application to specific research reactor. Following the intent of the available safety guides for surveillance and In-Service Inspection of Nuclear Power Plants, guidelines were formulated to develop surveillance and In-Service Inspection programme for research reactors Cirus and Dhruva. Based on the specific design of these research reactors, regulatory requirements, the degree of sophistication and experience of the technical organization involved in operating the research reactor, guidelines were evolved for developing and implementing the surveillance and In-Service Inspection programme for research reactors Cirus (40 MWt) and Dhruva (100 MWt) located at Bhabha Atomic Research Centre, Trombay, Mumbai, India. Paper describes the approach adopted for formulation of surveillance and In-service Inspection programme for Dhruva reactor in detail. (author)

  16. [Current status of job burnout in in-service sailors from 13 provinces and cities in China].

    Science.gov (United States)

    Shi, L C; Dai, J J; Wang, H R; Wang, J L; Miao, L Q; Yang, L R

    2017-12-20

    Objective: To investigate the current status of job burnout in in-service sailors, and to provide a basis for the development of intervention measures for job burnout in sailors. Methods: From September 2015 to May 2016, stratified cluster random sampling was used to select 6 172 in-service sailors from 13 provinces and cities as research subjects. General demographic data including age, education background, and household registration and occupational characteristics such as job position, navigating zone, and nature of employment were collected. The Maslach Burnout Inventory-General Survey (MBI-GS) was used to measure the levels of emotional exhaustion, depersonalization, low occupational efficiency, and job burnout, and the influencing factors for job burnout were also analyzed. Results: Of all 6 172 in-service sailors, 112 (1.8%) had a positive result in emotional exhaustion, 870 (14.1%) had a positive result in depersonalization, and 3 517 (57.0%) had a positive result in low occupational efficiency. Of all sailors, 63.3% had job burnout, among whom 54.1% had mild burnout, 8.7% had moderate burnout, and 0.5% had severe burnout. There was a significant difference in the score of job burnout between the sailors with different ages, education backgrounds, types of household registration, job positions, navigating zones, ornature of employment ( P burnout in in-service sailors ( P burnout in the sailors with an age of 30-39 years, education background of junior college or above, urban registration, a job position of second mate/third engineer, a navigating zone of coastal lines, orthe nature of employment of freelance sailor. Conclusion: There is a high incidence rate of job burnout among in-service sailors, and the sailors with a young age, urban registration, a navigating zone of coastal lines, or thenature of employment of freelance sailor tend to have low occupational efficiency. Related measures should be adopted for active intervention.

  17. The chatting gathering as a methodological strategy in in-service learning: moving along dialogical dynamics

    Directory of Open Access Journals (Sweden)

    María José Alonso

    2008-04-01

    Full Text Available This article focuses on an experience of in-service training carried out by a group of educators in literacy. The novelty of the undertaking lies in the methodological proposal analysed: using “chatting gatherings” as a methodological strategy, which supports critical reflection and the construction of knowledge, both in in-service training of professionals and in basic adult education. This experience reveals the nature of learning achieved through dialogical educational processes. Further, it allows us to observe the impact that they may have on the improvement of the professionals’ educational practices.

  18. Effect of Titanium on the Microstructure and Mechanical Properties of High-Carbon Martensitic Stainless Steel 8Cr13MoV

    Directory of Open Access Journals (Sweden)

    Wen-Tao Yu

    2016-08-01

    Full Text Available The effect of titanium on the carbides and mechanical properties of martensitic stainless steel 8Cr13MoV was studied. The results showed that TiCs not only acted as nucleation sites for δ-Fe and eutectic carbides, leading to the refinement of the microstructure, but also inhibited the formation of eutectic carbides M7C3. The addition of titanium in steel also promoted the transformation of M7C3-type to M23C6-type carbides, and consequently more carbides could be dissolved into the matrix during hot processing as demonstrated by the determination of extracted carbides from the steel matrix. Meanwhile, titanium suppressed the precipitation of secondary carbides during annealing. The appropriate amount of titanium addition decreased the size and fraction of primary carbides in the as-cast ingot, and improved the mechanical properties of the annealed steel.

  19. Decentralising Curriculum Reform: The Link Teacher Model of In-Service Training.

    Science.gov (United States)

    Wildy, Helen; And Others

    1996-01-01

    Presents a (Western Australian) case study of the link teacher model, a decentralized, "train the trainer" approach to inservice education. Discusses the model's perceived effectiveness, the link teachers' role, central authority support, and new experimentation opportunities. Combining centralized syllabus change with decentralized…

  20. Inservice trainings for Shiraz University of Medical Sciences employees: effectiveness assessment by using the CIPP model

    Directory of Open Access Journals (Sweden)

    MARYAM MOKHTARZADEGAN

    2015-04-01

    Full Text Available Introduction: Nowadays, the employees` inservice training has become one of the core components in survival and success of any organization. Unfortunately, despite the importance of training evaluation, a small portion of resources are allocated to this matter. Among many evaluation models, the CIPP model or Context, Input, Process, Product model is a very useful approach to educational evaluation. So far, the evaluation of the training courses mostly provided information for learners but this investigation aims at evaluating the effectiveness of the experts’ training programs and identifying its pros and cons based on the 4 stages of the CIPP model. Method: In this descriptive analytical study, done in 2013, 250 employees of Shiraz University Medical Sciences (SUMS participated in inservice training courses were randomly selected. The evaluated variables were designed using CIPP model and a researcher-made questionnaire was used for data collection; the questionnaire was validated using expert opinion and its reliability was confirmed by Cronbach’s alpha (0.89. Quantitative data were analyzed using SPSS 14 and statistical tests was done as needed. Results: In the context phase, the mean score was highest in solving work problems (4.07±0.88 and lowest in focusing on learners’ learning style training courses (2.68±0.91. There is a statistically significant difference between the employees` education level and the product phase evaluation (p0.001, in contrast with the process and product phase which showed a significant deference (p<0.001. Conclusion: Considering our results, although the inservice trainings given to sums employees has been effective in many ways, it has some weaknesses as well. Therefore improving these weaknesses and reinforcing strong points within the identified fields in this study should be taken into account by decision makers and administrators.

  1. Innovative Training of In-Service Teachers for Active Learning: A Short Teacher Development Course Based on Physics Education Research

    Science.gov (United States)

    Zavala, Genaro; Alarcon, Hugo; Benegas, Julio

    2007-01-01

    In this contribution we describe a short development course for in-service physics teachers. The course structure and materials are based on the results of educational research, and its main objective is to provide in-service teachers with a first contact with the active learning strategy "Tutorials in Introductory Physics," developed by…

  2. In-service inspection of nuclear power plants

    International Nuclear Information System (INIS)

    Asty, M.; Saglio, R.

    1984-10-01

    The French Commissariat a l'Energie Atomique (Atomic Energy Commission) developed two new non destructive control techniques, focused ultrasonics and multi-frequency eddy currents, which have been shown to allow a better detection and characterization of defects. We present here some of the in-service inspection devices which have been designed for field application of these techniques on the PWR reactors built by EDF, inspection devices of the PWR steam generator tubing and the now developing specific device for main tank and helicoidal tubing steam generator of Super-Phenix 1 [fr

  3. Impact of in-service education and training programmes on teachers ...

    African Journals Online (AJOL)

    Up to 80% of the teachers have participated in three or less INSET activities but only 10% of them said they engaged in activities that involved teaching reading methods in Social Studies. The paper therefore argues that in-service education and training programmes organized did little in exposing teachers to skills required ...

  4. A Study of Automation for Examination Analysis of Inservice Inspection for Nuclear Power Plant (I)

    International Nuclear Information System (INIS)

    Kim, W.

    1985-01-01

    The developing country, KOREA where does not possess the natural resources for traditional energy such as oil and gas, so. The nuclear energy is the most single reliable source available for closing the energy gap. For these reason, It is inavoidable to construct the nuclear power plant and to develop technology related nuclear energy. The rate of operation in large nuclear power facilities depends upon the performance of work system through design and construction, and also the applied technology. Especially, it is the most important element that safety and reliability in operation of nuclear power plant. In view of this aspects, Nuclear power plant is performed severe examinations during perceives and inservice inspection. This study provide an automation of analysis for volumetric examination which is required to nuclear power plant components. It is composed as follows: I. Introduction II. Inservice Inspection of Nuclear Power Plant * General Requirement. * Principle and Methods of Ultrasonic Test. * Study of Flaw Evaluation and Design of Classifying Formula for Flaws. III. Design of Automation for Flaw Evaluation. IV. An Example V. Conclusion In this theory, It is classifying the flaws, the formula of classifying flaws and the design of automation that is the main important point. As motioned the above, Owing to such as automatic design, more time could be allocated to practical test than that of evaluation of defects, Protecting against subjective bias tester by himself and miscalculation by dint of various process of computation. For the more, adopting this method would be used to more retaining for many test data and comparative evaluating during successive inspection intervals. Inspire of limitation for testing method and required application to test components, it provide useful application to flow evaluation for volumetric examination. Owing to the characteristics of nuclear power plant that is highly skill intensive industry and has huge system, the

  5. Dual roles and dual identities: enhancing the experience of in-service teacher training in English Further Education

    Directory of Open Access Journals (Sweden)

    Orr, Kevin

    2009-06-01

    Full Text Available In marked distinction from other sectors of education, around 90 percent of Further Education (FE staff in England are employed untrained and complete their Initial Teacher Training (ITT on a part-time in-service basis. By consequence, these staff sustain the dual role of employed teacher and teacher-trainee usually at the beginning of their career. This paper reports on a project funded by ESCalate which researched the dual roles and dual identities of employee and trainee on in-service FE teacher-training courses. It argues that the lack of a culture of pedagogical development in colleges along with the pressure for trainees to quickly cope with teaching can lead to conservative practice as expedience may be prioritised over flair. In response, the paper makes recommendations to enhance the experience and development of in-service teacher trainees.

  6. Effectiveness and reliability of US inservice inspection techniques

    International Nuclear Information System (INIS)

    Doctor, S.R.; Becker, F.L.; Selby, G.P.

    1982-01-01

    The work presented is from an ongoing program directed toward measuring the effectiveness and reliability of inservice inspection (ISI) of light water reactor systems (primary piping and pressure vessel). Extensive round robin and parametric evaluations have been conducted in 10 in. Sch. 80 stainless steel as well as centrifugally cast stainless steel and clad ferritic main coolant pipe welds. Results from these measurements will be viewed in relationship to US regulations and ASME Section XI Code requirements. 6 figures

  7. In-service quality assurance at the Fessenheim nuclear power plant

    International Nuclear Information System (INIS)

    Waller, A.

    1980-01-01

    Quality assurance is a combination of systematic and planned actions applied so as to give the adequate degree of confidence in the effective obtention of quality. Quality assurance is a daily requestioning resulting from systematic inspections and checks. The different principles permitting the in-service quality assurance system to be applied is presented [fr

  8. Quality control and in-service inspection technology for hybrid-composite girder bridges.

    Science.gov (United States)

    2014-08-01

    This report describes efforts to develop quality control tools and in-service inspection technologies for the fabrication and construction of Hybrid Composite Beams (HCBs). HCBs are a new bridge technology currently being evaluated by the Missouri De...

  9. Development of In-Service Inspection system for heat transfer tubes in the primary pressurized water cooler in the HTTR

    Energy Technology Data Exchange (ETDEWEB)

    Shinozaki, Masayuki; Furusawa, Takayuki [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Wada, Shigeyuki

    1999-08-01

    The ISI (In-Service Inspection) system has been developed so as to maintain the structural integrity of heat transfer tubes in the primary pressurized water cooler in the HTTR (High Temperature Engineering Test Reactor). This system consists of eddy current probes, ultra-sonic probes, insertion and extraction units, positioning unit and so on. Verification and performance tests of the developed ISI system were carried out using mock-up heat transfer tubes in the primary pressurized water cooler. The constitution of the system, R and D results of the inspection probes, and verification and performance test results of the ISI system for heat transfer tubes are described in this paper. (author)

  10. Inservice Elementary and Middle School Teachers' Conceptions of Photosynthesis and Respiration

    Science.gov (United States)

    Krall, Rebecca McNall; Lott, Kimberly H.; Wymer, Carol L.

    2009-01-01

    The purpose of this descriptive study was to investigate inservice elementary and middle school teachers' conceptions of photosynthesis and respiration, basic concepts they are expected to teach. A forced-choice instrument assessing selected standards-based life science concepts with non-scientific conceptions embedded in distracter options was…

  11. Preservice and Inservice Teachers' Perceptions of Appropriateness of Teacher Self-Disclosure

    Science.gov (United States)

    Zhang, Shaoan; Shi, Qingmin; Tonelson, Stephen; Robinson, Jack

    2009-01-01

    This study investigated preservice and inservice teachers' perceptions of appropriateness of teacher self-disclosure. A sample of 180 preservice teachers and 135 preK-12 teachers participated in the study. Results showed statistically significant differences between the groups of teachers in their perceptions of appropriateness of teacher…

  12. Preservice and In-Service Teachers' Perceptions toward Technology Benefits and Integration

    Science.gov (United States)

    Spaulding, Michael

    2013-01-01

    This study examined preservice teacher attitudes toward and expected technology integration practices as compared to in-service teachers' attitudes toward and actual (self-reported) practice of technology integration. The preservice teachers revealed a greater level of confidence in their ability to integrate technology and more positive beliefs…

  13. A data fusion approach for track monitoring from multiple in-service trains

    Science.gov (United States)

    Lederman, George; Chen, Siheng; Garrett, James H.; Kovačević, Jelena; Noh, Hae Young; Bielak, Jacobo

    2017-10-01

    We present a data fusion approach for enabling data-driven rail-infrastructure monitoring from multiple in-service trains. A number of researchers have proposed using vibration data collected from in-service trains as a low-cost method to monitor track geometry. The majority of this work has focused on developing novel features to extract information about the tracks from data produced by individual sensors on individual trains. We extend this work by presenting a technique to combine extracted features from multiple passes over the tracks from multiple sensors aboard multiple vehicles. There are a number of challenges in combining multiple data sources, like different relative position coordinates depending on the location of the sensor within the train. Furthermore, as the number of sensors increases, the likelihood that some will malfunction also increases. We use a two-step approach that first minimizes position offset errors through data alignment, then fuses the data with a novel adaptive Kalman filter that weights data according to its estimated reliability. We show the efficacy of this approach both through simulations and on a data-set collected from two instrumented trains operating over a one-year period. Combining data from numerous in-service trains allows for more continuous and more reliable data-driven monitoring than analyzing data from any one train alone; as the number of instrumented trains increases, the proposed fusion approach could facilitate track monitoring of entire rail-networks.

  14. Nondestructive examination (NDE) reliability for inservice inspection of light water reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Deffenbaugh, J.D.; Good, M.S.; Green, E.R.; Heasler, P.G.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.

    1989-10-01

    The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvement that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements based on material properties, service conditions, and NDE capabilities and uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other inspected components. This is a progress report covering the programmatic work from October 1987 through March 1988. 21 refs., 28 figs., 2 tabs

  15. Nondestructive examination (NDE) reliability for inservice inspection of light waters reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Deffenbaugh, J.D.; Good, M.S.; Green, E.R.; Heasler, P.G.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.

    1989-11-01

    Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other inspected components. This is a progress report covering the programmatic work from April 1988 through September 1988. 33 refs., 70 figs., 12 tabs

  16. Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Diaz, A.A.; Friley, J.R.

    1993-09-01

    The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other components inspected in accordance with Section XI of the ASME Code. This is a progress report covering the programmatic work from October 1991 through March 1992

  17. Status report on developments and cooperation on risk-informed inservice-inspection and non-destructive testing (NDT) qualification in OECD-NEA member countries - CSNI integrity and ageing working group

    International Nuclear Information System (INIS)

    Skanberg, Lars

    2005-01-01

    presented at the Workshop have been published in the proceedings referenced NEA/CSNI/R(2004)9. The two reports along with the NRWG-report EUR 21320 are the main source of information for this Status Report on Developments and Cooperation on Risk-Informed In-Service-Inspection and Non-Destructive Testing (NDT) Qualification in OECD-NEA member countries. The report is organized in the following way: introduction to early ISI strategies and Augmented ISI and NDT Qualification; Risk-Informed In-Service Inspection (RI-ISI): Development of RI-ISI strategies, RI-ISI Regulatory guidance, Important aspects of RI-ISI, Overview of RI-ISI methods, Comparison of methods, Overview of RI-ISI applications and pilot studies, RI-ISI experience so far, Further evaluations and developments of RI-ISI methodologies; Non-Destructive Testing (NDT) Qualification: Development of NDT qualification strategies, NDT-qualification requirements and applications, NDT-qualification experience. Conclusions and recommendations are then given

  18. Training model to institutionalize population education in the in-service education programme for elementary school teachers.

    Science.gov (United States)

    Dugenia, M E

    1982-12-01

    The goal of the Philippine Population Education Program (PEP) since its inception in 1972 is to institutionalize population education in the formal educational system. The PEP Training Section views institutionalization of population education in the inservice education program for elementary school teachers as part of the process of making it an integral part of that program. In practice elementary school teachers periodically attend training programs organized by division or district supervisors and school principals. This is the usual modality through which teachers are updated on or informed about new thrusts and recent developments in teaching content, strategies, and methodologies. In this context, the PEP Training Section convened a seminar workshop in December 1981 for 10 subject area supervisors from the 3 large geographic island groups of Luzon, Visayas, and Mindanao. They represented 10 school divisions and subject areas where population education is integrated. The specific objectives of the 5 day activity were to: discuss existing inservice training programs in the school divisions; prepare a training model incorporating population education in the overall division inservice training program; and develop a content chart or a listing of topical areas on population education for the training model. 1 of the outputs of the seminar workshop was a training model incorporating population education in the regular inservice training programs using 3 delivery schemes, i.e., seminar workship on the teaching of specific subject areas; district staff meeting and/or echo seminars organized by district supervisors following division seminars; and regular teachers' meeting at the school level organized by school principals. Another output was a content chart listing suggested topics in population education classified according to subject areas into which they will be incorporated. The semninar workshop concluded with a plan to try out the model using the identified

  19. An Experimental Investigation of the Effectiveness of Inservice Teacher Education in Thailand.

    Science.gov (United States)

    Nitsaisook, Malee; Anderson, Lorin W.

    1989-01-01

    Results are reported from an experimental study involving 97 fifth grade math teachers in Thailand to determine whether participation in an inservice teacher education program directly influenced teachers' teaching practices and indirectly influenced the learning of their students. (IAH)

  20. Relationship among science teacher personality characteristics and degree of teacher classroom implementation after in-service workshop

    Science.gov (United States)

    Sechler, Phares Lochiel Coleman

    State departments of public instruction require that teachers periodically update their licenses throughout their teaching careers. Various professional development events such as in-service workshops, university offerings, and special innovative programs provide opportunities for novice and experienced teachers to grow professionally. The "Team Science" workshop was designed from models supported by research that described guidelines for successful workshop strategies. In evaluating the workshop, the question was asked "Why did not all teachers implement the ideas from the workshop in their science classrooms?" This study investigates the possible relationship between teacher personality characteristics and implementation of technology innovations. Team Science was an extensive workshop program planned to develop science teachers' expertise in using computer and video technology to teach in physical science, chemistry, and physics classrooms in rural school in North Carolina. Upon evaluating the four-year effort, it was found that the 23 participants implemented the technological strategies at various levels. At the higher end of the range of technology use, some teachers exhibited complete integration of the computers and interfacing devices into both the laboratory work and the classroom inquiry. At the lower end of the range, some teachers used the technology very little. The resulting question emerged from the data collected: Do specific teacher personality characteristics (independent variables) correlate with the degree of implementation (dependent variable) of the innovative ideas and tools used in the teacher's science classroom after the in-service workshop? To determine if there were any significant personality traits, each teacher was given five personality tests. The tests were Hunt's Conceptual Development Test, the Paragraph Completion Test; James Rest's Defining Issues Test; Simmons Personal Survey, an emotional tendency test; the Myers-Briggs Type

  1. Interdisciplinary Program For In-Service Teachers; Working with Industry And University to Enhance Learning Experiences in the State of Ohio (Invited Paper

    Directory of Open Access Journals (Sweden)

    Suzanne Lunsford

    2014-12-01

    Full Text Available Science Teaching for Ohio's New Economy (STONE is an interdisciplinary professional development program that inservice teachers grades K-12 that experience the integration of earth and physical science in an inquiry-based field. There are various field trips to various industrial settings that teach how geoscientist works in the aggregate industry. During the academic year there is a support system where the industry and the in-service teachers engage their students into real world industrial applications in the aggregate industry. This paper will discuss the utilization of high – tech instrumentation such as X-Ray Fluorescence and Scanning Electron Microscopy to teach real-world science applications of concern. Pre- and Post-test assessments as addressed by R.R. Hake have shown that these inquirybased professional development workshops that integrated academia with industry as a positive outcome for our students in Ohio.

  2. Automated [inservice testing] IST program

    International Nuclear Information System (INIS)

    Wright, W.M.

    1990-01-01

    There are two methods used to manage a Section XI program: Manual and Automated. The manual method usually consists of hand written records of test results and scheduling requirements. This method while initially lower in cost, results in problems later on in the life of a plant as data continues to accumulate. Automation allows instant access to forty years of test results. Due to the lower cost and higher performance of todays' personal computers, an automated method via a computer program provides an excellent method for managing the vast amount of data that accumulates over the forty year life of a plant. Through the use of a computer, special functions involving this data are available, which through a manual method would not be practical. This paper will describe some of the advantages in using a computer program to manage the Section XI 1ST program. The ISTBASE consists of program code and numerous databases. The source code is written and complied in CLIPPER (tm) language. Graphing routines are performed by dGE (tm) graphics library. Graphs are displayed in EGA form. Since it was estimated that the total complied code, would exceed 640K of ram, overlays through the use of modular programming were used to facilitate the DOS restrictions of 640K ram. The use of overlays still require the user to gain access to ISTBASE through the PASSWORD module. The database files are designed to be compatible with dBASE III+ (tm) data structure. This allows transfer of data between ISTBASE and other database managers/applications. A math co-processor is utilized to speed up calculations on graphs and other mathematical calculations. Program code and data files require a hard disk drive with at least 28 Meg capacity. While ISTBASE will execute on a 8088 based computer, an 80286 computer with a 12 MHz operating speed should be considered the minimum system configuration

  3. In-Service Training of Teachers as Behavior Modifiers: Review and Analysis.

    Science.gov (United States)

    Eachus, Herbert Todd

    The basic principles of operant and classical conditioning are presented, and their applications for the in-service training of teachers are discussed. Certain classroom behaviors are analyzed and applied to the classic stimulus-response paradigm. Activities are generically classified as positive or negative reinforcers and these reinforcers, in…

  4. Assessing the Impact of In-Service Training on Staff Performance at ...

    African Journals Online (AJOL)

    performance in terms of knowledge and skills gained. It was recommended that more research is undertaken on all UEW campuses to add to both literature and knowledge of INSET. Keywords: Staff Performance, In-Service Training, Staff Development International Journal of Educational Research Vol. 3 (2) 2007 pp. 217- ...

  5. The Impact of In-Service Technology Training Programmes on Technology Teachers

    Science.gov (United States)

    Gumbo, Mishack; Makgato, Moses; Muller, Helene

    2012-01-01

    The aim of this paper is to assess the impact the Advanced Certificate in Education (ACE) in-service technology training program has on technology teachers' knowledge and understanding of technology. The training of technology teachers is an initiative toward teachers' professional development within the mathematics, science, and technology sphere…

  6. Case studies of beliefs of two in-service primary school teachers ...

    African Journals Online (AJOL)

    Within the mathematics teacher education program, a variety of teaching strategies and theories are discussed with the aim of changing the student teachers views about mathematics and its teaching. This study was conducted with two in-service primary school teachers as they progressed through a 4-year degree ...

  7. Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection

    Energy Technology Data Exchange (ETDEWEB)

    Vo, T.V.; Smith, B.W.; Simonen, F.A.; Gore, B.F.

    1994-08-01

    The goals of the Evaluation and Improvement of Non-destructive Examination Reliability for the In-service Inspection of Light Water Reactors Program sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory (PNL) are to (1) assess current ISI techniques and requirements for all pressure boundary systems and components, (2) determine if improvements to the requirements are needed, and (3) if necessary, develop recommendations for revising the applicable ASME Codes and regulatory requirements. In evaluating approaches that could be used to provide a technical basis for improved inservice inspection plans, PNL has developed and applied a method that uses results of probabilistic risk assessment (PRA) to establish piping system ISI requirements. In the PNL program, the feasibility of generic ISI requirements is being addressed in two phases. Phase I involves identifying and prioritizing the systems most relevant to plant safety. The results of these evaluations will be later consolidated into requirements for comprehensive inservice inspection of nuclear power plant components that will be developed in Phase II. This report presents Phase I evaluations for eight selected plants and attempts to compare these PRA-based inspection priorities with current ASME Section XI requirements for Class 1, 2 and 3 systems. These results show that there are generic insights that can be extrapolated from the selected plants to specific classes of light water reactors.

  8. Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection

    International Nuclear Information System (INIS)

    Vo, T.V.; Smith, B.W.; Simonen, F.A.; Gore, B.F.

    1994-08-01

    The goals of the Evaluation and Improvement of Non-destructive Examination Reliability for the In-service Inspection of Light Water Reactors Program sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory (PNL) are to (1) assess current ISI techniques and requirements for all pressure boundary systems and components, (2) determine if improvements to the requirements are needed, and (3) if necessary, develop recommendations for revising the applicable ASME Codes and regulatory requirements. In evaluating approaches that could be used to provide a technical basis for improved inservice inspection plans, PNL has developed and applied a method that uses results of probabilistic risk assessment (PRA) to establish piping system ISI requirements. In the PNL program, the feasibility of generic ISI requirements is being addressed in two phases. Phase I involves identifying and prioritizing the systems most relevant to plant safety. The results of these evaluations will be later consolidated into requirements for comprehensive inservice inspection of nuclear power plant components that will be developed in Phase II. This report presents Phase I evaluations for eight selected plants and attempts to compare these PRA-based inspection priorities with current ASME Section XI requirements for Class 1, 2 and 3 systems. These results show that there are generic insights that can be extrapolated from the selected plants to specific classes of light water reactors

  9. In-Service Training of Teachers in Multicultural Urban Schools: A Systematic Model.

    Science.gov (United States)

    Nickolai-Mays, Susanne; Davis, Jerry L.

    1986-01-01

    Presents seven guidelines for developing effective teacher in-service training programs. Describes a training model for multicultural urban schools which addresses these topics: instructional methods; curriculum; interpersonal relations in the classroom; classroom management and discipline; parent-teacher-student involvement; and multicultural…

  10. In-service inspection as an aid to steel pressure vessel reliability

    International Nuclear Information System (INIS)

    Nichols, R.W.

    1975-01-01

    In-service inspection has played an important role in non-nuclear pressure vessel technology, being a legal requirement in many countries. Evidence from surveys of reliability of non-nuclear plant has suggested that such inspections can be effective in reducing the risk of subsequent failures. Recent requirements of the ASME XI code which will be summarised have important implications on the techniques to be used for in-service inspection, and so on design and fabrication aspects. Moreover, in-service inspection can only be an effective procedure if its possible weaknesses are recognised. The first problem is to ensure that an ultrasonic technique is used which is capable of detecting defects of an order of magnitude smaller than the critical size for each particular situation, in whatever defect orientation is important. The potential of different ultrasonic techniques will be compared. Next it is necessary to ensure coverage of all the relevant material. In this respect machine operation is superior to manual scanning, so that manipulation and scanning devices have to be developed. Problems of local geometry and of deviations in geometry have to be discussed with designer and fabricator; plate and clad quality have to be controlled (with respect to surface contour, metallurgical condition and freedom from interfering defects) to ensure inspectability in depth. The reliability of the mechanical and electronic equipment has to be assessed and designed to meet high requirements. Some presentational aids to detection and interpretation will be discussed. Having located a potential defect, the application of fracture mechanics treatments requires knowledge of size, shape and orientation. Some of the problems will be discussed together with possible solutions. (author)

  11. Application of risk-informed in-service inspection approach. Pilot study on low pressure emergency core cooling system of NPP Temelin

    International Nuclear Information System (INIS)

    Horacek, L.; Palyza, J.; Zdarek, J.; Vizina, M.

    2004-01-01

    In-service inspection (ISI) programme of piping systems based on Riskinformed In-service Inspections (RI-ISI) approach represents for the WWER NPP licensee first overall systematic conceptual solution of the problems associated with design and design modifications of ISI programme for piping systems. The approach enables to consider possible savings and comparison of in-service inspection programmes according to more objective criteria including those calculated in PSA, in contrast to present much empiric experience collected by manufacturers, operators and ISI vendors in the past. Service experience has shown limited correlation between the deterministic ISI requirements and actual field failures or degradation mechanisms. Where field failures have been observed in piping, they have generally been due to either material concerns (e.g., Intergranular Stress Corrosion Cracking) or stress/cycling mechanisms not identified in the original design basis documents (e.g., thermal stratification), and therefore would not be selected for inspection under current requirements. Risk-informed in-service inspections represent integrated multidisciplinary approach to the in-service inspection programme fulfilling the enhanced requirements of the Czech Regulatory Body (SUJB) for defence in depth concept applied to weld joints of safety related components, application of qualified NDT methods/techniques and introducing of inspections for cause approach. Inspections for cause take into account analysis of both active and potential degradation mechanisms specific to piping system concerned. Simultaneously, this approach enables the licensee to reach, in cases justified from safety point of view, economic savings resulting from lowering of both number and extent of performed in-service inspections and optimisation of their performance. RI ISI pilot study based in majority on EPRI methodology implemented for WWER type reactors has been performed for LP ECCS (Low Pressure Emergency

  12. Demonstration test of in-service inspection methods

    International Nuclear Information System (INIS)

    Takumi, Kenji

    1987-01-01

    The major objectives of the project are: (1) to demonstrate the reliability of a manual ultrasonic flaw detector and techniques that are used in operating light water reactor plants and (2) to demonstrate the performance and reliability of an automatic ultrasonic flaw detector that is designed to shorten the time required for ISI work and reduce the exposure risk of inspection personnel. The test project consists of three stages. In the first stage, which ended in 1982, defects were added intentionally to a model structure the same in size as a typical 1.1 million kW BWR plant and manual ultrasonic flaw detection tensting was performed. In the second stage, completed in 1984, automatic eddy-current flaw detection testing was carried out for defects in heat transfer piping of a PWP steam generator. In the third stage, which started in 1981 and ended in March 1987, a newly developed automatic ultrasonic flaw detector is applied to testing of defects used for the manual detector performance evaluation. Results have shown that the automatic eddy-current flaw detector under test has an adequately stable performance for practical uses, with a very high reproducibility to permit close inspection of secular deterioration in heat transfer pipes. It has also revealed that both the manual and automatic ultrasonic flaw detectors under test can detect all defects that do not comply with the ASME standards. (Nogami, K.)

  13. Aligning In-Service Training Examinations in Plastic Surgery and Orthopaedic Surgery With Competency-Based Education.

    Science.gov (United States)

    Ganesh Kumar, Nishant; Benvenuti, Michael A; Drolet, Brian C

    2017-10-01

    In-service training examinations (ITEs) are used to assess residents across specialties. However, it is not clear how they are integrated with the Accreditation Council for Graduate Medical Education Milestones and competencies. This study explored the distribution of specialty-specific milestones and competencies in ITEs for plastic surgery and orthopaedic surgery. In-service training examinations were publicly available for plastic surgery (PSITE) and orthopaedics (OITE). Questions on the PSITE for 2014-2016 and the OITE for 2013-2015 were mapped to the specialty-specific milestones and the 6 competencies. There was an uneven distribution of milestones and competencies in ITE questions. Nine of the 36 Plastic Surgery Milestones represented 52% (341 of 650) of questions, and 3 were not included in the ITE. Of 41 Orthopaedic Surgery Milestones, 7 represented 51% (201 of 394) of questions, and 5 had no representation on the ITE. Among the competencies, patient care was the most common (PSITE = 62% [403 of 650]; OITE = 59% [233 of 394]), followed by medical knowledge (PSITE = 34% [222 of 650]; OITE = 31% [124 of 394]). Distribution of the remaining competencies differed between the 2 specialties (PSITE = 4% [25 of 650]; OITE = 9% [37 of 394]). The ITEs tested slightly more than half of the milestones for the 2 specialties, and focused predominantly on patient care and medical knowledge competencies.

  14. Development process of in-service training intended for teachers to perform teaching of mathematics with computer algebra systems

    Science.gov (United States)

    Ardıç, Mehmet Alper; Işleyen, Tevfik

    2018-01-01

    In this study, we deal with the development process of in-service training activities designed in order for mathematics teachers of secondary education to realize teaching of mathematics, utilizing computer algebra systems. In addition, the results obtained from the researches carried out during and after the in-service training were summarized. Last section focuses on suggestions any teacher can use to carry out activities aimed at using computer algebra systems in teaching environments.

  15. Enhanced InService Inspection system for BWR plant

    International Nuclear Information System (INIS)

    Shouji, Hajime; Kobayashi, Teruo; Nagao, Tetsuya

    1993-01-01

    An enhanced InService Inspection system (ISI) has been developed, consisting of newly designed automated scanners, automated pipe inspection system and a high speed data acquisition/analysis station. This system uses a trackless magnetic crawler type nozzle inspection scanner attached to the nozzle shoulder by magnetic wheels. The automated pipe inspection system consists of an automated scanner, controller and high speed data acquisition station. These advanced automatic inspection systems are very useful for ISI, especially in reducing the radiation exposure and time required. (author)

  16. An attempt for empowering education: A qualitative study of in-service training of nursing personnel

    Directory of Open Access Journals (Sweden)

    Mahmood Chaghari

    2016-01-01

    Full Text Available Background: In-service training of nursing personnel has a significant role in increasing the empowerment of nurses and promotion of the quality of health services. The objective of this study is to identify and explain the process of in-service training of nursing personnel in the hospitals affiliated with Baqiyatallah University of Medical Sciences in Tehran. Materials and Methods: The present study employed a qualitative approach using Corbin and Strauss method (2008 in 2015, and examined the viewpoints and experiences of 35 nurses, nurse managers, and educational managers with the in-service education of nursing staffs. According to this method, comparisons, asking questions, flip-flop technique, depicting personal experiences, and raising red flag were used for data analysis. Results: In this study, five major themes including unsuccessful mandatory education, empowering education, organizational challenges, weakness in the educational management, and educational-job resiliency were derived from the results. Unsuccessful mandatory education was the main concern of participants and empowering education was the core category derived from this study. Conclusions: Empowering education emphasizes the practice-oriented and self-directed training. It is an applied education, is participation-oriented, facilitates job functions, and is based on exploration.

  17. An attempt for empowering education: A qualitative study of in-service training of nursing personnel.

    Science.gov (United States)

    Chaghari, Mahmood; Ebadi, Abbas; Ameryoun, Ahmad; Safari, Mohsen

    2016-01-01

    In-service training of nursing personnel has a significant role in increasing the empowerment of nurses and promotion of the quality of health services. The objective of this study is to identify and explain the process of in-service training of nursing personnel in the hospitals affiliated with Baqiyatallah University of Medical Sciences in Tehran. The present study employed a qualitative approach using Corbin and Strauss method (2008) in 2015, and examined the viewpoints and experiences of 35 nurses, nurse managers, and educational managers with the in-service education of nursing staffs. According to this method, comparisons, asking questions, flip-flop technique, depicting personal experiences, and raising red flag were used for data analysis. In this study, five major themes including unsuccessful mandatory education, empowering education, organizational challenges, weakness in the educational management, and educational-job resiliency were derived from the results. Unsuccessful mandatory education was the main concern of participants and empowering education was the core category derived from this study. Empowering education emphasizes the practice-oriented and self-directed training. It is an applied education, is participation-oriented, facilitates job functions, and is based on exploration.

  18. RIBA Project - Risk-Informed approach for In-Service Inspection of Nuclear Power Plant Components. Project summary

    International Nuclear Information System (INIS)

    Lidbury, D.; Smith, G.

    2001-12-01

    The need for a European review of a Risk-Informed Approach for In-Service Inspection of Nuclear Power Plant Components (RIBA) was identified in 1998. This was as a priority item in the programme of activities conducted in the framework of the Council Resolutions of 22 July 1975 and of 18 June 1992 on the Technological Problems of Nuclear Safety. The RIBA Project was established in November 1999 as a 24-month Study Contract funded by the European Commission within the frame of the former DG XI WGCS (Working Group on Codes and Standards). The Study Contract was subsequently managed for the EC by DG TREN. The participants in RIBA were Serco Assurance (project coordinator), Ringhals AB, EDF, Tecnatom SA and Westinghouse Electric Europe. The work is presented in a summary report with the detailed results contained in three companion reports as follows: main conclusions and recommendations, Review of Existing Risk-Informed Methodologies, A Comparative Study of Risk-Informed In-Service Inspection Applications, Conclusions and Recommendations for Risk-Informed in-service inspection methodology applied to Nuclear Power Plants in Europe. (author)

  19. Test plan for the irradiation of nonmetallic materials.

    Energy Technology Data Exchange (ETDEWEB)

    Brush, Laurence H.; Farnum, Cathy Ottinger; Gelbard, Fred; Dahl, M.; Joslyn, C. C.; Venetz, T. J.

    2013-03-01

    A comprehensive test program to evaluate nonmetallic materials use in the Hanford Tank Farms is described in detail. This test program determines the effects of simultaneous multiple stressors at reasonable conditions on in-service configuration components by engineering performance testing.

  20. Test plan for the irradiation of nonmetallic materials.

    Energy Technology Data Exchange (ETDEWEB)

    Brush, Laurence H.; Farnum, Cathy Ottinger; Dahl, M.; Joslyn, C. C.; Venetz, T. J.

    2013-05-01

    A comprehensive test program to evaluate nonmetallic materials use in the Hanford tank farms is described in detail. This test program determines the effects of simultaneous multiple stressors at reasonable conditions on in-service configuration components by engineering performance testing.

  1. Impacts of an In-Service Education Program on Promoting Language Development in Young Children: A Pilot Study with Early Childhood Educators

    Science.gov (United States)

    Scarinci, Nerina; Rose, Tanya; Pee, Jerrine; Webb, Kylie

    2015-01-01

    Early childhood educators (ECEs) play an important role in fostering language development in young children. In-service education, led by speech-language pathologists (SLPs), has a potential role in educating ECEs about language development. In this pilot study, 42 ECEs attended an in-service education program and completed pre- and…

  2. In-Service and Pre-Service Early Childhood Teachers' Views and Intentions about ICT Use in Early Childhood Settings: A Comparative Study

    Science.gov (United States)

    Gialamas, Vasilis; Nikolopoulou, Kleopatra

    2010-01-01

    This paper regards a comparative study which investigates in-service and pre-service Greek early childhood teachers' views and intentions about integrating and using computers in early childhood settings. Views and intentions were investigated via a questionnaire administered to 240 in-service and 428 pre-service early childhood teachers.…

  3. Pre-Service and In-Service Secondary School Teachers' Knowledge about Attention-Deficit Hyperactivity Disorder (ADHD) and Attitudes toward Students with ADHD

    Science.gov (United States)

    Liang, Limeng; Gao, Xuesong

    2016-01-01

    This article reports on a mixed-method inquiry into pre-service and in-service secondary school teachers' knowledge about Attention-deficit Hyperactivity Disorder (ADHD) and attitudes toward students with this disorder in Hong Kong. The inquiry revealed no differences between pre-service and in-service secondary school teachers concerning their…

  4. Unpacking In-Service EFL Teachers' Critical Incidents: The Case of Iran

    Science.gov (United States)

    Atai, Mahmood Reza; Nejadghanbar, Hassan

    2016-01-01

    Despite the importance of reflection on critical incidents (CIs), there are only a few studies in ELT literature addressing English language teachers' CIs (Farrell, 2008). Accordingly, this study was conducted to explore and discuss how six in-service EFL teachers reflected on and reported their CIs. In so doing, the participant teachers reflected…

  5. Emotional Creativity (EC) among Pre-Service and In-Service Trainee Teachers

    Science.gov (United States)

    Singh, Gaurav; Kumar, Girijesh

    2010-01-01

    In the personality of a teacher, his emotional creativity is an important counterpart. In current study, researchers have carried out an investigation of emotional creativity of trainee teachers of pre-service and in-service trainee teachers. The objectives were to compare the emotional creativity of Trainee teachers of Pre-service Courses and…

  6. X-ray tomographic in-service testing of girth welds - The European project TomoWELD; Roentgen-tomographische In-Service-Pruefung von Rundschweissnaehten. Das Europaeische Projekt TomoWELD

    Energy Technology Data Exchange (ETDEWEB)

    Ewert, Uwe; Redmer, Bernhard; Walter, David; Thiessenhusen, Kai-Uwe; Bellon, Carsten [BAM Bundesanstalt fuer Materialforschung und -pruefung, Berlin (Germany); Nicholson, P. Ian; Clarke, Alan [TWI Technology Centre, Port Talbot (United Kingdom); Finke-Haerkoenen, Klaus-Peter [Ajat Oy Ltd., Espoo (Finland); Scharfschwerdt, Joerg W.; Rohde, Karsten [AREVA GmbH, Erlangen (Germany)

    2015-07-01

    The new standard ISO 17636-2: 2013 'NDT of welded joints - Radiographic testing - Part 2: X- and gamma radiographic testing with digital detectors ''defines the testing practice for digital radiography of welds for the production and in-service inspection. Furthermore the DIN 25435-7:2014 ''In-service inspections of the components of the primary circuit of light water reactors - Part 7: Radiographic testing'' was published. The essential requirements are discussed. The new TomoWELD system can both perform measurements according to these standards as well as record tomographic cross-sectional images (equivalent to metallographic sections), to determine image sizes. Areas of application are chemical and nuclear facilities. It provides a fast testing of girth welds as compared to the use of film or imaging plates. In 2006 the mechanized planar tomography system, TomoCAR, was already introduced, with one could measure cross-sectional images. TomoWELD uses a new photon counting and energy resolving detector with CdTe-CMOS crystal hybrids. The new detector allows the choice of energy thresholds, and enables the reduction of the influence of scattered radiation on the radiographic images and the reconstructed cross-sectional images. An optimized irradiation geometry with a new manipulator design and a fast GPU-based reconstruction algorithm can be used to accelerate the reconstruction and to improve the reconstruction results. The size and the shape of planar and voluminous irregularities can be determined. The concept and the first pictures will be presented. (Contains mainly PowerPoint slides). [German] Der neue Standard ISO 17636-2:2013 ''ZfP von Schweissnaehten - Durchstrahlungspruefung - Teil 2: Roentgen- und Gammastrahlungstechniken mit digitalen Detektoren'' definiert die Pruefpraxis fuer die digitale Radiographie von Schweissnaehten fuer die Herstellung und In-Service- Pruefung. Ausserdem wurde die DIN 25435

  7. 77 FR 69508 - Inservice Inspection of Prestressed Concrete Containment Structures With Grouted Tendons

    Science.gov (United States)

    2012-11-19

    ... Containment Structures With Grouted Tendons AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide... (RG) 1.90, ``Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons... appropriate surveillance program for prestressed concrete containment structures with grouted tendons...

  8. Valve testing for UK PWR safety applications

    International Nuclear Information System (INIS)

    George, P.T.; Bryant, S.

    1989-01-01

    Extensive testing and development has been done by the Central Electricity Generating Board (CEGB) to support the design, construction and operation of Sizewell B, the UK's first PWR. A Blowdown Rig for the Assessment of Valve Operability - (BRAVO) has been constructed at the CEGB Marchwood Engineering Laboratory to reproduce PWR Pressurizer fluid conditions for the full scale testing of Pressurizer Relief System (PRS) valves. A full size tandem pair of Pilot Operated Safety Relief Valves (POSRVs) is being tested under the full range of pressurizer fluid conditions. Tests to date have produced important data on the performance of the valve in its Cold Overpressure protection mode of operation and on methods for the in-service testing of the valve. Also, a full size pressurizer safety valve has been tested under full PRS fluid conditions to develop a methodology for the pre-service testing of the Sizewell valves. Further work will be carried out to develop procedures for the in-service testing of the valve. In the Main Steam Safety Valve test program carried out at the Siemens-KWU Test Facilities, a single MSSV from three potential suppliers was tested under full secondary system conditions. The test results have been analyzed and are reflected in the CEGB's arrangements for the pre-service and in-service testing of the Sizewell MSSVs. Valves required to interrupt pipebreak flow must be qualified for this duty by testing or a combination of testing and analysis. To obtain guidance on the performance of such tests gate and globe valves have been subjected to simulated pipebreaks under PWR primary circuit conditions. In the light of problems encountered with gate valve closure under these conditions, further tests are currently being carried out on the BRAVO facility on a gate valve, in preparation for the full scale flow interruption qualification testing of the Sizewell main steam isolation valve

  9. After-production and in-service inspections of components of nuclear power plant primary coolant circuits

    International Nuclear Information System (INIS)

    Slama, K.; Svetlik, M.

    1990-01-01

    A new diagnostic system was developed for detecting defects in the material of mechanically loaded equipment. It is based on the measurement of elastic strain waves propagating through the materials. The instrument units as well as the methodology and software are of Czechoslovak origin and can be modified to conform to the requirements and experience of the user. The way of applying the method to the diagnostics of pressure vessels, main circulation pumps of the pressurizers and of the primary piping is described. Some results of after-production and in-service acoustic emission tests are given, as are the technical parameters of the acoustic emission analyzer. (M.D.). 5 figs

  10. Identification of areas and time intervals for inservice inspections; Auswahl der Pruefbereiche und -intervalle fuer wiederkehrende Pruefungen

    Energy Technology Data Exchange (ETDEWEB)

    Metzner, K J [Preussische Elektrizitaets-AG (Preussenelektra), Hannover (Germany); Herter, K H [Stuttgart Univ. (Germany). Staatliche Materialpruefungsanstalt; Schoeckle, F [Amtec Messtechnischer Service, Lauffen (Germany)

    1998-11-01

    Inservice inspections are an important, redundant part of the overall concept for ensuring component integrity during NPP operation. Their efficiency however has to be considered in the context of measures creating required component quality (design and manufacture), and inspection and monitoring measures maintaining the quality of components. If an available system for inservice monitoring yields comprehensive information about real inservice loads (monitoring of the causes of degradation), inservice inspections can be designed to purposefully check the possibly resulting damaging modes and defects. If there is no or only low-level monitoring, the possible consequences of possibly damaging mechanisms that may be unknown should be checked by expanded inservice inspections plus, if necessary, unspecific, random inspections. For selection of inspection areas and determination of inspection intervals, use of design-based analyses which take into account conservative, specified loads and load frequencies (for operating modes and incidents) is not recommendable. The recommended approach is to take as a basis information on measured, real inservice loads together with information about the real quality status of components, derived from manufacturing data and service histories. The available information has to be scanned and processed so as to give a basis for new appraisal of hitherto applied NDE methods. (orig./CB) [Deutsch] Wiederkehrende Pruefungen sind ein wichtiger redundanter Teil der Gesamtmassnahmen zur Gewaehrleistung der Komponentenintegritaet waehrend des Betriebes von Kernkraftwerken. Ihre Wirksamkeit muss jedoch in enger Verbindung mit den die Komponentenqualitaet erzeugenden Massnahmen (Auslegung und Herstellung) und den die Komponentenqualitaet erhaltenden Ueberwachungmassnahmen waehrend des Betriebes gesehen werden. Wenn die vorhandene Betriebsueberwachung eine umfassende Kenntnis der bisherigen Betriebsbelastungen ermoeglicht (Ueberwachung der Ursachen

  11. State-of-practice review of ultrasonic in-service inspection of Class I system piping in commercial nuclear power plants

    International Nuclear Information System (INIS)

    Morris, C.J.; Becker, F.L.

    1982-08-01

    The Pacific Northwest Laboratory conducted a survey to determine the state of practice of ultrasonic in-service inspection of primary system piping in light water reactors. Personnel at four utilities, five inspection organizations, and three domestic reactor manufacturers were interviewed. The intention of the study was to provide a better understanding of the actual practices employed in in-service inspection of primary system piping and of the difficulties encountered

  12. Evaluation of effectiveness of inservice inspection in aging PWR plants based on PSA

    Energy Technology Data Exchange (ETDEWEB)

    Hanafusa, Hidemitsu; Irie, Takashi; Suyama, Takeshi [Institute of Nuclear Safety Systems Inc., Mihama, Fukui (Japan); Morota, Hidetsugu [Computer Software Development Co., Ltd., Tokyo (Japan)

    2001-09-01

    By making use of a probabilistic fracture mechanics (PFM) code which had been improved to be able to evaluate the influence of thermal aging embrittlement of cast stainless steel, we evaluated the fracture probability of welding parts of the piping of the pressurized water reactor plants in Japan and the core damage frequency by the fracture. In addition, we ranked the welding parts by the safety significance and evaluated the effectiveness of inservice inspection (ISI). As a result, it is seen that the risk increases about 25% for extending the plant life from 40 to 60 years without ISI. However, the influence of the risk on the plant life becomes negligible, when the ISI is performed adequately. This assessment is useful to plan efficient inspection and test programs of a plant under limited resources, because it is available to rank piping segments by the safety significance and to evaluate the effectiveness of inspection and test quantitatively. (author)

  13. Application of phased arrays in basic and in-service inspection

    International Nuclear Information System (INIS)

    Gebhardt, W.; Schwarz, H.P.; Bonitz, F.; Woll, H.

    1985-01-01

    In the scope of the reactor safety research program of the Federal Ministry of Research and Technology a flexible microcomputer controlled phased array system was developed. Meanwhile, several industrial prototypes for simple and complicated applications are built up. The applicability of phased array systems in NDE for basic and inservice inspections of reactor pressure vessels is investigated. Methods for defect detection, reconstruction and classification are described

  14. Preventing degradation and in-service inspection of NPP steam generator

    International Nuclear Information System (INIS)

    Ding Xunshen

    1999-01-01

    The author describes the degradation of steam generator tubes in initial operating stage of France NPP. The author emphatically presents the preventive measures to tackle degradation and In-service inspection of Daya Bay NPP 1 unit as a guarantee of safety operation, including secondary side water chemistry monitoring and controlling, leakage rate monitoring, eddy-current inspection, mechanical cleaning, cleanliness inspection, foreign objects removal and etc

  15. An overview of in-service inspection for nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Takano, Eishiro

    1996-01-01

    In nuclear power stations, for maintaining the safety of machinery and equipment, it is stipulated to carry out periodic inspection. The contents of the periodic inspection and the inspections of important matters are explained. In-service inspection (ISI) is the nondestructive inspection for confirming the soundness of reactor pressure vessels, main pipings, valves and others. The stipulations on the scope and time of the periodic inspection and ISI, the course of introducing ISI into Japan, and the basic way of thinking on ISI are described. Pre-service inspection (PSI) is carried out for the purpose of collecting and recording the initial data for ISI. The range of the objects of nondestructive inspection and leak test and the range of the objects of leak test only are shown. As to nondestructive inspection, the parts to be inspected, the frequency of inspection and the methods of inspection, and the method of leak test are described. As the present state of inspection technology, the automatic ultrasonic flow detectors for reactor vessels, piping welded parts and reactor vessel stud bolts, and the eddy current flaw detector for steam generator tubes are explained. (K.I.)

  16. Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Diaz, A.A.; Friley, J.R.; Good, M.S.; Greenwood, M.S.; Heasler, P.G.; Hockey, R.L.; Kurtz, R.J.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V.

    1992-07-01

    The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWR's); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to the Regulatory and ASME Code requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other components inspected in accordance with Section XI of the ASME Code. This is a progress report covering the programmatic work from April 1991 through September 1991

  17. Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Diaz, A.A.; Friley, J.R.; Greenwood, M.S.; Heasler, P.G.; Kurtz, R.J.; Simonen, F.A.; Spanner, J.C.; Vo, T.V.

    1993-11-01

    The Evaluation and Improvement of NDE Reliability for Inservice inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs);using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to the Regulatory and ASME Code requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel and other components inspected in accordance with Section XI of the ASME Code. This is a programs report covering the programmatic work from April 1992 through September 1992

  18. Nondestructive examination (NDE) reliability for inservice inspection of light water reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Good, M.S.; Green, E.R.; Heasler, P.G.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V.

    1991-08-01

    The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other components inspected in accordance with Section 6 of the ASME Code. This is a progress report covering the pro grammatic work from April 1989 through September 1989. 12 refs., 4 figs. 5 tabs

  19. Experience with ANSI N14.30 for in-service inspections of semi-trailer used for spent fuel shipments

    International Nuclear Information System (INIS)

    Hirtz, G.J.

    1998-05-01

    On July 18, 1996, the Oak Ridge National Laboratory (ORNL) resumed shipping spent fuel in interstate commerce after a 10 year suspension of this activity. This shipment was conducted using a Nuclear Regulatory Commission licensed spent fuel transport package purchased from General Electric Company by ORNL for the purpose of moving High Flux Isotope Reactor spent fuel to the Savannah River Site. The trailer, fabricated to the ANSI N14.30, Semi-Trailers Employed in the Highway Transport of Weight Concentrated Radioactive Loads Design, Fabrication, and Maintenance, has recently undergone its first scheduled in-service inspection. This paper presents the experience gained from interpretation and application of the ANSI N14.30 standard focusing on the in-service inspection for the structure of the trailer. Initially, the term weight concentrated is illustrated giving detail to the location and center of gravity of the 33,500 pound shipping container and forces induced by the tie down system. Basic information about the design stresses and initial testing provided by the manufacturer are used as a lead-in to the requirements of the standard. The task of examining the trailer structure provided many lessons and required considerable effort. All of the support personnel were provided by ORNL; the garage mechanics and the certified inspection engineers had never been involved in applying ANSI N14.30. Other obstacles were the lack of existing inspection procedures for this particular activity and the lack of a previous experience interpreting the standard with regard to repair work. Some of these questions were resolved by clarification received from the writers of the standard, and others were resolved by the teamwork between the manufacturer and ORNL. This experience illustrated the importance of the trailer manufacturer as a participant in the decisions made concerning in-service inspection and maintenance

  20. In-Service Physical Educators' Experiences of Online Adapted Physical Education Endorsement Courses.

    Science.gov (United States)

    Sato, Takahiro; Haegele, Justin A; Foot, Rachel

    2017-04-01

    The purpose of this study was to investigate in-service physical education (PE) teachers' experiences during online adapted physical education (APE) graduate courses. Based on andragogy theory (adult learning theory) we employed a descriptive qualitative methodology using an explanatory case study design. The participants (6 female and 3 male) were in-service PE teachers enrolled in an online graduate APE endorsement program. Data collection included journal reflection reports and face-to-face interviews. A constant comparative method was used to interpret the data. Three interrelated themes emerged from the participants' narratives. The first theme, instructor communication, exposes the advantages and disadvantages the participants perceived regarding communication while enrolled in the online APE graduate courses. The second theme, bulletin board discussion experiences, described participants' perceptions of the use of the bulletin board discussion forum. Lastly, the final theme, assessment experiences, described how the participants learned knowledge and skills through online courses related to assessment and evaluation.

  1. Relationships between needle and syringe programs and police: An exploratory analysis of the potential role of in-service training.

    Science.gov (United States)

    Strike, Carol; Watson, Tara Marie

    2017-06-01

    Training police on the public health benefits of needle and syringe programs (NSPs) is viewed as a best practice to facilitate more collaborative relationships between police and these programs. To date, while the limited published literature contains promising cases of harm reduction in-service training for police, evaluative evidence is preliminary. Using an online survey, we asked NSP managers across Canada about their programs and the quality of their NSP-police relationships. We analyzed data from the responses of 75 program managers among whom 69% reported that their program had a "positive" or "mostly positive" relationship with the police. In-service training about topics such as needle-stick injury prevention and NSP effectiveness was provided by less than 50% of the programs surveyed. Seventy-five percent reported no established protocols to resolve conflicts between NSP staff and police. Four variables, all related to in-service training, were significantly related to positive NSP-police relationships, including training about: NSP program goals (OR 7.7; 95% CI 2.0, 33.1); needle-stick injury prevention and basics of blood-borne virus transmission (OR 4.0; 95% CI 1.1, 15.34); the health and social concerns of people who use drugs (OR 3.9; 95% CI 1.1, 13.5); and evidence about the impact of injection equipment distribution (OR 3.9; 95% CI 1.1, 13.5). Development of in-service training for police that is focused on harm reduction goals and initiatives is a new and evolving area. We highly encourage NSPs to offer and evaluate any such in-service training programs. Copyright © 2017 Elsevier B.V. All rights reserved.

  2. New Swedish regulations in the area of plant inspection and in-service inspection

    International Nuclear Information System (INIS)

    Hansson, B.

    1998-01-01

    History and present status od Swedish regulations in the field of NPP inspection and in-service inspection are described. The presentation focuses on the development of regulations and establishing new ones. A description of different organisations involved is included

  3. Using Drawing as Intervention with Children for In-Service Preschool Teachers

    Science.gov (United States)

    Chen, I Ju; Liu, Chu Chih

    2010-01-01

    This study provides a basic overview of in-service preschool teachers using drawing as intervention with children. Art therapy is used more often for the smaller children who have more difficulty to describe their emotions and feelings in recognizing words, such as anger, resentment, and different kind of abuses. As a matter of fact, the drawing…

  4. Opinion on the demonstration of the 900 MWe reactor vessels in-service behaviour after their third decennial inspection

    International Nuclear Information System (INIS)

    2010-01-01

    In this report, an expert group comments and assesses how sufficient are the demonstration and the actions performed by EDF to justify the in-service behaviour of nuclear reactor vessels. More precisely, it comments and discusses the different steps of the EDF demonstration: follow-up of the fluence received by the vessels, identification of the most severe transients and thermodynamic calculations, behaviour of irradiated materials, mechanical analysis, in-service control and follow-up plan, ageing management. Recommendations are then formulated

  5. A fracture mechanics and reliability based method to assess non-destructive testings for pressure vessels

    International Nuclear Information System (INIS)

    Kitagawa, Hideo; Hisada, Toshiaki

    1979-01-01

    Quantitative evaluation has not been made on the effects of carrying out preservice and in-service nondestructive tests for securing the soundness, safety and maintainability of pressure vessels, spending large expenses and labor. Especially the problems concerning the time and interval of in-service inspections lack the reasonable, quantitative evaluation method. In this paper, the problems of pressure vessels are treated by having developed the analysis method based on reliability technology and probability theory. The growth of surface cracks in pressure vessels was estimated, using the results of previous studies. The effects of nondestructive inspection on the defects in pressure vessels were evaluated, and the influences of many factors, such as plate thickness, stress, the accuracy of inspection and so on, on the effects of inspection, and the method of evaluating the inspections at unequal intervals were investigated. The analysis of reliability taking in-service inspection into consideration, the evaluation of in-service inspection and other affecting factors through the typical examples of analysis, and the review concerning the time of inspection are described. The method of analyzing the reliability of pressure vessels, considering the growth of defects and preservice and in-service nondestructive tests, was able to be systematized so as to be practically usable. (Kako, I.)

  6. Comparative Analysis of Expectancies of Efficacy in In-Service and Prospective Teachers

    Science.gov (United States)

    de la Torre Cruz, Manuel J.; Casanova Arias, Pedro F.

    2007-01-01

    This study examines the beliefs about effective teaching in student teachers and inservice teachers. We constructed a measurement composed of an adaptation in Spanish of the Gibson and Dembo's (1984. Teacher efficacy: A construct validation. "Journal of Educational Psychology", 76, 569-582). Teacher Efficacy Scale and of the items…

  7. Agricultural In-Service Needs of Introductory Level Career and Technical Education Teachers

    Science.gov (United States)

    Christensen, Jolene; Warnick, Brian K.; Spielmaker, Debra; Tarpley, Rudy S.; Straquadine, Gary S.

    2009-01-01

    This study identified and prioritized the agricultural in-service needs of introductory level career and technical education teachers in Utah. The Utah State Board of Education requires that all seventh grade students complete an introductory career and technical education course as their first formal career exploration experience. One component…

  8. An Inservice Staff Development Program for Vocational Teachers Working with Disadvantaged Students.

    Science.gov (United States)

    Wircenski, Jerry L.; Just, David

    1984-01-01

    To serve the inservice needs of vocational teachers of the disadvantaged, an instructional resource team visited area vocational-technical schools in Pennsylvania weekly for 10 weeks. Summative evaluation showed that a majority of the 42 teachers serving 280 students received assistance with resource identification, diagnosis, and curriculum and…

  9. Pre-Service and In-Service Teachers' Metacognitive Knowledge about Problem-Solving Strategies

    Science.gov (United States)

    Metallidou, Panayiota

    2009-01-01

    The present study based on Antonietti, A., Ignazi, S., & Perego, P. (2000). Metacognitive knowledge about problem-solving methods. "British Journal of Educational Psychology, 70", 1-16 methodology with the aim to examine primary school teachers' metacognitive knowledge about problem-solving strategies. A sample of 338 in-service (172) and…

  10. Motor-operated Valve Program at NPP Krsko (NEK) - Status and Overview

    International Nuclear Information System (INIS)

    Nikolic, M; Jagodar, N.; Cerjak, J.; Butkovic, V.

    2002-01-01

    On the basics of US NRC Generic Letter 89-10 Safety-related Motor-operated Valve Testing and Surveillance and subsequent generic letters, Motor-operated Valve (MOV) Program at NEK has been developing. Namely, the holders of nuclear power plant operating licenses has to verify the design basis capability of safety-related e.g. important-to-safety MOVs, as well as to ensure the same for the life of the plant. In light of that, each plant should establish a program to address stressed issues for each program MOV (124 at NEK). Such comprehensive task requires significant effort in many aspects, and basically multidisciplinary skills. NEK MOV Program represents a blend of engineering and in-plant testing, comprised of three phases: Phase I Engineering, Phase II Field Implementation and Phase III Trending. Currently, the program is about the end of Phase I and II, as well as in development of engineering basis for launching Phase III. Overview of the major programmatic issues will be given in this paper along with ongoing activities: testing process, gear-ratio modification, pressure locking/thermal binding susceptibility screening and preventive maintenance. (author)

  11. RSE-M: In-Service Inspection Rules for Mechanical Components of PWR Nuclear Islands

    International Nuclear Information System (INIS)

    2016-01-01

    The RSE-M code defines in-service inspection operations. It applies to pressure equipment used in PWR plants, as well as spare parts for such equipment. The RSE-M code does not apply to equipment made from materials other than metal. It is based on the RCC-M code for requirements relating to the design and fabrication of mechanical components. Use: The inspection rules specified in the RSE-M code describe the standard requirements of best practice within the French nuclear industry, based on its own feedback from operating several nuclear units and partly supplemented with requirements stipulated by French regulations. To date, the 58 units in France's nuclear infrastructure enforce the in-service inspection rules of the RSE-M code. Operation of 30 commissioned units in China's nuclear infrastructure, corresponding to the M310, CPR-1000 and CPR-600 reactors, is based on the RSE-M code (since 2007, use of AFCEN codes has been required by NNSA for Generation II+ reactors). Contents of the 2016 Edition: Volume I - Rules: Section A - General rules, Section B - Specific rules for class 1 components, Section C - Specific rules for class 2 or 3 components, Section D - Specific rules for components not assigned to any particular RSE-M class; Volume II - Appendices 1 to 8: Appendices 1.0 to 1.9: supporting appendices for the general requirements, Appendix 2.1: appendix associated with chap. 2000 Requalifications, Hydraulic Proof Tests and Hydraulic Tests, Appendices 4.1 to 4.4: appendices associated with chap. 4000 Examination techniques, Appendices 5.1 to 5.8 and RPP2: appendices associated with chap. 5000 Mechanical and Materials, Appendices 8.1 to 8.2: appendices associated with chap. 8000 Maintenance Operations; Volume III: Appendix 3.1 - Visit tables: main primary and secondary systems, EPR pre-service inspection program, Class 2 or 3 vessels; Appendix 3.2 - Inspection Plans For Non-Nuclear Pressure Equipment

  12. IN-SERVICE TEACHER TRAINING COURSES: ORGANIZATIONAL COMPONENTS

    Directory of Open Access Journals (Sweden)

    Mykola Solovey

    2017-07-01

    Full Text Available The article describes the organizational components of the teacher training courses at the Khmelnytsky Regional In-Service Teacher Training Institute. According to the Law of Ukraine “On Professional Development” the state policy in this area aims at the process of continuous professional development and creates conditions for teacher to learn at training courses once every five years. The Law of Ukraine "On Education" declares that the professional development is the duty and the rate of life of teachers. Formation of the number of trainees, the quality of the scientific and pedagogical staff, the content of training, planning and documentation, resources and economic support are the basis for organizing in-service courses. The formation of a contingent of trainees consists of several stages: 1 previous research and prediction of the quantitative composition of trainees; 2 specification of indicators of the actual number of trainees; 3 approval of the actual number of trainees, and the schedule for the next year's courses; 4 an analysis of the implementation of the plan of courses. Every year more than six thousand teachers study at the courses. In accordance with the schedule of training, students are spread across departments. Lecture sessions, practical sessions, trainings are carried out by the scientific staff of the departments, methodologists and teachers of practice. Educational programs are built on the basis of qualification characteristics, state requirements for the content of education in secondary school, the wishes of teachers. The overall structure of the programs corresponds to the recommendations of the Ministry of Education and Science of Ukraine. The variable part is developed in accordance with the pedagogical specialties and considering the recommendations of the departments and methodologists. Based on the content of educational programs, the general structure of the curriculum is developed. The institute has

  13. Factors that influence acceptance of web-based e-learning systems for the in-service education of junior high school teachers in Taiwan.

    Science.gov (United States)

    Chen, Hong-Ren; Tseng, Hsiao-Fen

    2012-08-01

    Web-based e-learning is not restricted by time or place and can provide teachers with a learning environment that is flexible and convenient, enabling them to efficiently learn, quickly develop their professional expertise, and advance professionally. Many research reports on web-based e-learning have neglected the role of the teacher's perspective in the acceptance of using web-based e-learning systems for in-service education. We distributed questionnaires to 402 junior high school teachers in central Taiwan. This study used the Technology Acceptance Model (TAM) as our theoretical foundation and employed the Structure Equation Model (SEM) to examine factors that influenced intentions to use in-service training conducted through web-based e-learning. The results showed that motivation to use and Internet self-efficacy were significantly positively associated with behavioral intentions regarding the use of web-based e-learning for in-service training through the factors of perceived usefulness and perceived ease of use. The factor of computer anxiety had a significantly negative effect on behavioral intentions toward web-based e-learning in-service training through the factor of perceived ease of use. Perceived usefulness and motivation to use were the primary reasons for the acceptance by junior high school teachers of web-based e-learning systems for in-service training. Copyright © 2011 Elsevier Ltd. All rights reserved.

  14. Design considerations, tooling and equipment for remote in-service inspection of radioactive piping and pressure vessel systems

    International Nuclear Information System (INIS)

    Schmoker, D.S.; Swannack, D.L.

    1983-01-01

    In-Service Inspection programs are performed to monitor and verify the integrity of a nuclear power plant's primary pressure boundaries. Early detection of abnormal structural or material degradation could preclude serious damage to plant systems. This paper summarizes results obtained in use of remotely-operated nondestructive testing (NDT) equipment for inspection of reactor system components. Experience obtained in operating the Fast Flux Test Facility (FFTF) has provided a basis for field verification of remote NDT equipment designs and has suggested development improvements. Remote Viewing and data gathering systems used include periscopes, borescopes, fiberscopes, hybrid borescopes/fiberscopes, and closed circuit television. A summary of design consideration for inspection equipment and power plant design is presented to achieve improved equipment operation and reduction of plant maintenance downtime

  15. Distance Support In-Service Engineering for the High Energy Laser

    Science.gov (United States)

    2015-03-01

    FEL only) o Isoplanatic angle (if available) o Fried coherence length o Object distance o Dwell time o Laser spot size While many of the items...system and the HEL system. Acquisition Sensor Laser Subsystem Beam Shaping Sensor Suile . Range Finder -. Coarse Tracker . Fine Tracker Optical...distribution is unlimited DISTANCE SUPPORT IN-SERVICE ENGINEERING FOR THE HIGH ENERGY LASER by Team Raising HEL from a Distance Cohort 311-133O March

  16. Pump testing - Comparison of factory vs. field test of centrifugal pumps

    International Nuclear Information System (INIS)

    Fehlau, R.

    1992-01-01

    Testing of pumps in situ, i.e., as installed in a system, will typically yield somewhat different performance results from the original manufacturer's factory test. This paper discusses some of the reasons for these variations. It shows that the factory test curves can be used for evaluation of initial acceptance tests but not for reference in normal inservice testing (IST). This is the basis for reference values used in American Society of Mechanical Engineers (ASME) Section 11 specifications and the revised ASME Code 1990

  17. Attributes of Pre-Service and Inservice Teacher Satisfaction with Online Collaborative Mentoring

    Science.gov (United States)

    Dorner, Helga; Kumar, Swapna

    2017-01-01

    This study examines Hungarian pre-service and inservice teachers' satisfaction (n = 154) with the Mentored Innovation Model (MIM), an online collaborative mentoring model focused on technology integration. The Kano model was applied to results from two surveys to identify conditions in the MIM that most contribute to overall satisfaction with…

  18. Mathematics and Multilingual Learners: Transformative Learning through In-Service Teacher Professional Development

    Science.gov (United States)

    Holdway, Jennifer

    2016-01-01

    In response to the increasing linguistic and cultural diversity in US schools, in-service teachers are faced with the significant challenge of addressing both the linguistic and instructional needs of their multilingual learners (MLLs). This study provides evidence of the linguistic obstacles faced in the academic mathematics classroom and how…

  19. Teacher Competency in Classroom Testing, Measurement Preparation, and Classroom Testing Practices.

    Science.gov (United States)

    Newman, Dorothy C.; Stallings, William M.

    An assessment instrument and a questionnaire (Appendices A and B) were developed to determine how well teachers understand classroom testing principles and to gain information on the measurement preparation and classroom practices of teachers. Two hundred ninety-four inservice teachers, grades 1 through 12, from three urban school systems in…

  20. Chat It Up: Backchanneling to Promote Reflective Practice among In-Service Teachers

    Science.gov (United States)

    Kassner, Laura D.; Cassada, Kate M.

    2017-01-01

    In a graduate education course geared toward developing reflective teaching practice in in-service teachers, backchannels, in the form of chat rooms, were employed in small groups to facilitate peer feedback during viewings of video recorded instruction. This study examined the nature and quality of peer feedback exchanged in the digital medium…

  1. Career Intentions and Experiences of Pre- and In-Service Female Band Teachers

    Science.gov (United States)

    Fischer-Croneis, Sarah H.

    2016-01-01

    The purpose of this study was to examine pre- and in-service female band teachers' perspectives regarding their experiences in realizing their professional goals. Domains guiding this inquiry included (a) gaining entry into the profession of band teaching, (b) navigating the profession, and (c) gender issues. Findings from this multiple case study…

  2. Exploring In-Service Preschool Teachers' Conceptions of and Approaches to Online Education

    Science.gov (United States)

    Yang, Yu-Fang; Tsai, Chin-Chung

    2017-01-01

    This paper reports on an investigation of adult online learning for 91 Taiwanese in-service preschool teachers enrolled in online degree programs. By using an open-ended written essay to investigate what learners thought they were learning through online education (their conceptions) and how they engaged in online education (their approaches),…

  3. For the Horticulture Teacher--A Personal In-Service Program Can Keep You Relevant.

    Science.gov (United States)

    Karns, Christine D.

    1980-01-01

    To keep current with industry changes, the vocational horticulture instructor can join horticulture industry associations, utilize horticulture outlets for field trips, use horticulture experts as resource persons, work in the industry, participate in university-sponsored inservice programs, attend industry association workshops and seminars, and…

  4. Advanced In-Service Inspection Approaches Applied to the Phenix Fast Breeder Reactor

    International Nuclear Information System (INIS)

    Guidez, J.; Martin, L.; Dupraz, R.

    2006-01-01

    The safety upgrading of the Phenix plant undertaken between 1994 and 1997 involved a vast inspection programme of the reactor, the external storage drum and the secondary sodium circuits in order to meet the requirements of the defence-in-depth safety approach. The three lines of defence were analysed for every safety related component: demonstration of the quality of design and construction, appropriate in-service inspection and controlling the consequences of an accident. The in-service reactor block inspection programme consisted in controlling the core support structures and the high-temperature elements. Despite the fact that limited consideration had been given to inspection constraints during the design stage of the reactor in the 1960's, as compared to more recent reactor projects such as the European Fast Reactor (EFR), all the core support line elements were able to be inspected. The three following main operations are described: Ultrasonic inspection of the upper hangers of the main vessel, using small transducers able to withstand temperatures of 130 deg. C, Inspection of the conical shell supporting the core dia-grid. A specific ultrasonic method and a special implementation technique were used to control the under sodium structure welds, located up to several meters away from the scan surface. Remote inspection of the hot pool structures, particularly the core cover plug after partial sodium drainage of the reactor vessel. Other inspections are also summarized: control of secondary sodium circuit piping, intermediate heat exchangers, primary sodium pumps, steam generator units and external storage drum. The pool type reactor concept, developed in France since the 1960's, presents several favourable safety and operational features. The feedback from the Phenix plant also shows real potential for in-service inspection. The design of future generation IV sodium fast reactors will benefit from the experience acquired from the Phenix plant. (authors)

  5. Dialogismo, decodificação e marketin digital interativo em torno das práticas corporais no festival on-line de vídeos olympikus.mov - doi: 10.5007/2175-8042.2010n34p136

    OpenAIRE

    Godoi, Marcos Roberto; Secretaria Estadual do CBCE-MT

    2010-01-01

    The aim was to understand the meanings associated bodily practices in the videos of the festival OLYMPIKUS.MOV, and also analyze the reception/interaction Internet users on these videos. The methodology consisted the description of the videos, the selection of comments and further analysis based on the notion of dialogic language of Mikhail Bakhtin and the types of decoding Stuart Hall. We concluded that there was a large range of bodily practices and meanings related to them in the videos. R...

  6. Significant issues and changes for ANSI/ASME OM-1 1981, part 1, ASME OMc code-1994, and ASME OM Code-1995, Appendix I, inservice testing of pressure relief devices in light water reactor power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seniuk, P.J.

    1996-12-01

    This paper identifies significant changes to the ANSI/ASME OM-1 1981, Part 1, and ASME Omc Code-1994 and ASME OM Code-1995, Appendix I, {open_quotes}Inservice Testing of Pressure Relief Devices in Light-Water Reactor Power Plants{close_quotes}. The paper describes changes to different Code editions and presents insights into the direction of the code committee and selected topics to be considered by the ASME O&M Working Group on pressure relief devices. These topics include scope issues, thermal relief valve issues, as-found and as-left set-pressure determinations, exclusions from testing, and cold setpoint bench testing. The purpose of this paper is to describe some significant issues being addressed by the O&M Working Group on Pressure Relief Devices (OM-1). The writer is currently the chair of OM-1 and the statements expressed herein represents his personal opinion.

  7. Significant issues and changes for ANSI/ASME OM-1 1981, part 1, ASME OMc code-1994, and ASME OM Code-1995, Appendix I, inservice testing of pressure relief devices in light water reactor power plants

    International Nuclear Information System (INIS)

    Seniuk, P.J.

    1996-01-01

    This paper identifies significant changes to the ANSI/ASME OM-1 1981, Part 1, and ASME Omc Code-1994 and ASME OM Code-1995, Appendix I, open-quotes Inservice Testing of Pressure Relief Devices in Light-Water Reactor Power Plantsclose quotes. The paper describes changes to different Code editions and presents insights into the direction of the code committee and selected topics to be considered by the ASME O ampersand M Working Group on pressure relief devices. These topics include scope issues, thermal relief valve issues, as-found and as-left set-pressure determinations, exclusions from testing, and cold setpoint bench testing. The purpose of this paper is to describe some significant issues being addressed by the O ampersand M Working Group on Pressure Relief Devices (OM-1). The writer is currently the chair of OM-1 and the statements expressed herein represents his personal opinion

  8. Conceptual design and assessment of in-service inspection and maintenance of KALIMER

    Energy Technology Data Exchange (ETDEWEB)

    Joo, Young Sang; Kim, Seok Hun; Kim, Jong Bum; Lee, Jae Han [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-05-01

    In the conceptual design stage of KALIMER, the philosophy and methodology of in-service inspection (ISI) and maintenance for the reactor system and components are proposed and described. The ISI and maintenance should be carried out throughout plant life to ensure the structural integrity and safety of KALIMER. The conceptual design of ISI and maintenance are performed for considering the design characteristics of KALIMER and the intents of the ASME XI Division 3. This report describes and summarizes the requirements and available methods of ISI and maintenance. The visual inspection and continuous monitoring play a great role in the in-service inspection of KALIMER. The major structures of KALIMER reactor system are designed for maintenance free operation for the plant life time and the maintenance philosophy is to replace major components rather than repair them. The assessment of the ISI accessibility and maintainability is performed and reviewed each major component. The postulated failure defects for each component are estimated and evaluated for KALIMER safety and reliability. 8 refs., 16 figs., 13 tabs. (Author)

  9. The Effects of In-Service Training Seminars on the Tourism Marketing Role of Professional Tour Guides

    Directory of Open Access Journals (Sweden)

    Sezer Korkmaz

    2011-06-01

    Full Text Available This study has investigated that how the compulsory in-service training seminars have affected the attitudes composing marketing function of guides. Questionnaire has aimed to investigate that there are meaningful satisfaction level differences between or among the guides in respect to their various qualifications. Unstructured interview and participant observation methods have also been conducted. It has been seen that the satisfaction level of guides from in-service training seminars is quite low. The research findings show that there are meaningful differences between the attitudes of marketing function of guides who are not attended and attended to marketing related seminars. It has been seen that marketing related seminars have positive effects on guides’ marketing related attitudes.

  10. The Mechatronic System Design Of Ultrasonic Scanner For Inservice Inspection Of Research Reactor

    Science.gov (United States)

    Handono, Khairul; Kristedjo, K.; Awwaluddin, M.; Shobary, Ihsan

    2018-02-01

    The mechatronic system design of ultrasonic scanner for inservices inspection of Research Reactor has been conducted. The requirement designed must be reliable operated, safety to personnel and equipments, ease of maintenance and operation, protection of equipment mechanically, interchangeability of equipments and addition of the several model of probe immersion ultrasonic tranducer. In order to achieve the above goals and obtain the desired results, a mechatronic design based on mechanical and electronic practical experiences will be needed. In this paper consist of the mechanical design and the system mechanical movement using stepper motor control. The criteria and the methods of designs of mechanical and electronic equipments of the system have been discussed and investigated. A mechanical and instrumentation control system drawing and requirement of design will be presented as the outcome of the design. The designed of mechanical system is consequently simulated by solidwork software. The intention of the above research is to create solutions in different ways of inservice inspection of integrity of Reactor.

  11. Recent changes in code requirements for repair of in-service pipelines by welding

    Energy Technology Data Exchange (ETDEWEB)

    Bruce, W.A. [Edison Welding Inst., Columbus, OH (United States)

    2000-07-01

    Corrosion damage on pipelines represents the second most important cause of damage to natural gas pipelines in the United States. The area containing the corrosion damage must be reinforced to prevent the pipeline to rupture and from bulging. The predominant method of reinforcing corrosion damage in cross-country pipelines is to install a full-encirclement repair sleeve. The recent up-date of American Petroleum Institute (API) code requirement for repair of in-service pipelines by welding was published to provide a recommended practice for pipeline maintenance welding. The recent changes to the code are explained. The appendix B to the up-date is intended to alleviate redundancy between API 1104 and API 1107 and the time lag between up-dates, and to address technological advances made in the area of in-service welding. An alternative repair method of deposited weld metal, or weld deposition repair is briefly explained. 9 refs., 5 figs.

  12. In-service inspection of fertilizer and steel and ship building industries

    International Nuclear Information System (INIS)

    Sanaullah, Md.

    1998-01-01

    There is a good number of fertilizer factories, and steel and ship building industries in Bangladesh. Different NDT methods are being used for in-service inspection of these industries to ensure product reliability, to prevent accident and save human life, to maintain a uniform quality level, to lower manufacturing cost and to minimize the wastage of time and materials and for other benefits. (author)

  13. Individualized Inservice Teacher Education (Project In-Step). Evaluation Report. Phase III.

    Science.gov (United States)

    Thurber, John C.

    This is a report on the third phase of Project IN-STEP, which was intended to develop a viable model for individualized, multi-media in-service teacher education programs. (Phase I and II are reported in ED 033 905, and ED 042 709). The rationale for Phase III was to see if the model could be successfully transferred to an area other than teaching…

  14. Prioritization of motor operated valves based on risk importances

    International Nuclear Information System (INIS)

    Vesely, W.E.; Weidenhamer, G.H.

    1994-01-01

    The plant Probabilistic Risk Assessment (PRA) can be a potentially useful and powerful tool for helping to define an effective response to GL 89-10. The plant PRA can be used to prioritize the Motor Operated Valves (MOV) dynamic test. The plant PRA can also be used to determine test schedules for the MOVs. In order for the PRA to be validly used to respond to GL 89-10, various issues need to be validly addressed. Eleven issues are specifically identified and responses to these issues are outlined. The issues of joint MOV importance, PRA truncation, and validation of the proposed approach are specifically highlighted and more detailed response considerations are described. As in all PRA applications, sensitivity studies and uncertainty considerations should be incorporated in the PRA evaluations. 4 refs, 3 tabs

  15. Qualification of NDT systems for in-service inspections of nuclear power plant pressure vessels; Ydinvoimalaitosten paineastioiden maeaeraeaikaistarkastuksissa kaeytettaevien NDT-jaerjestelmien paetevoeinti

    Energy Technology Data Exchange (ETDEWEB)

    Elfving, K

    1998-11-01

    The goal of this study is to determine the requirements of the in-service inspection qualification in Europe, their feasibility in practice and to find out possible manufacture defects in test pieces used in practical trials. The literature study consists of qualification requirements set by European regulatory bodies and by the European nuclear power utilities. Also a brief summary of qualification requirements set by ASME Code, Section XI and comparison between ASME and European qualification requirements is included 24 refs.

  16. In-service education and teachers’ perception about key competences development with Sport Education

    Directory of Open Access Journals (Sweden)

    Antonio Calderón

    2013-01-01

    Full Text Available The purpose of this paper was to analyze the perception of physical education teachers on job opportunities of key competences of a particular teaching model. To this end, 12 teachers, Secondary and Primary, conducted an in-service education course on the model, and once completed, implemented a teaching unit in their respective schools. It was then through a questionnaire, they were asked about their perception of the development of key competences. To check whether there were differences in the perception of teachers on the development of each of the core competencies, it was calculated means and standard deviations of all variables recorded, and used the Mann-Whitney U test for independent samples. Teachers see great potential to work competence through Sport Education Model primarily on social and civic competence, lifelong learning, and autonomy and personal initiative.

  17. Report on the Regulators Experience of NDT Qualification for In-service Inspection of Nuclear Components

    International Nuclear Information System (INIS)

    2003-08-01

    In November 1992, the Nuclear Regulators Working Group (NRWG) decided to set up a task force on qualification of non-destructive testing (NDT) systems for pre and in-service inspection of light water reactors. The first task was to agree on the philosophy and principles governing the qualification of techniques, equipment, software, procedures, and personnel for NDT to be used for the inspection of structural components that are important to safety in nuclear power plants; and to establish a common view on essential aspects of NDT qualifications. The first task, which also included a comparison of the common views of the European regulators with the qualification approach outlined in Appendix VIII to Section XI of the ASME Code, was completed in 1996. The result was published in the report ''Common position of European regulators on qualification of NDT systems for pre- and in-service inspection of light water reactor components''2. In parallel, the European nuclear power industries had set up a working group, the European Network for Inspection Qualification (ENIQ), to discuss and agree on how to perform inspection qualifications. In 1995, ENIQ finalized its first version of ''European methodology for qualification of non-destructive tests''3. A second version 4 was then published in 1997. This second version is in relatively close agreement with the principles given in the regulators common position document. With these two basic documents, a platform was established for the further development of qualification strategies in the European countries. The second task of the NRWG Task Force was to follow and evaluate the first ENIQ pilot study from a regulatory point of view. The objective of this pilot study was to explore ways of how to apply the European qualification methodology and to test its feasibility. The pilot study commenced late 1996 and was planned to be finalized a year later. Depending on unforeseen difficulties, the pilot study has been delayed

  18. Elementary Preservice Teachers' and Elementary Inservice Teachers' Knowledge of Mathematical Modeling

    Science.gov (United States)

    Schwerdtfeger, Sara

    2017-01-01

    This study examined the differences in knowledge of mathematical modeling between a group of elementary preservice teachers and a group of elementary inservice teachers. Mathematical modeling has recently come to the forefront of elementary mathematics classrooms because of the call to add mathematical modeling tasks in mathematics classes through…

  19. The Development of Qualitative Classroom Action Research Workshop for In-Service Science Teachers

    Science.gov (United States)

    Buaraphan, Khajornsak

    2016-01-01

    In-service science teachers in Thailand are mandated to conduct classroom research, which can be quantitative and qualitative research, to improve teaching and learning. Comparing to quantitative research, qualitative research is a research approach that most of the Thai science teachers are not familiar with. This situation impedes science…

  20. Proceedings of the 4th NRC/ASME symposium on valve and pump testing

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    The 1996 Symposium on Valve and Pump Testing, jointly sponsored by the Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the U.S. Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. Individual papers of this Proceedings have been cataloged separately.

  1. Proceedings of the 4th NRC/ASME symposium on valve and pump testing

    International Nuclear Information System (INIS)

    1996-01-01

    The 1996 Symposium on Valve and Pump Testing, jointly sponsored by the Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the U.S. Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. Individual papers of this Proceedings have been cataloged separately

  2. Design, Implementation and Analysis of Learner-Centered Guided In-Service Programme for Technical Teacher Education

    Directory of Open Access Journals (Sweden)

    Tiia Rüütmann

    2014-03-01

    Full Text Available The design of learner-centered guided in-service program for technical teacher education has been launched at Estonian Centre for Engineering Pedagogy at Tallinn University of Technology. The aim of the program has been facilitating the initial in-service teaching experience, involving mentoring, peer support and cognitive apprenticeship. The emphasis has been on teaching for knowledge application, including the choice of content and processes, motivation, reflection, problem-solving, choice of educational technology, effective teaching methods, teaching models and strategies ཿ concepts, tools and procedures of the field of engineering, organized in ways enabling teachers to formulate real world problems, apply and solve them. The program has been implemented since 2012 and covers IGIP curriculum requirements. In the present article the designed program is described and analyzed.

  3. A case-mix in-service education program.

    Science.gov (United States)

    Arons, R R

    1985-01-01

    The new case-mix in-service education program at the Presbyterian Hospital in the City of New York is a fine example of physicians and administration working together to achieve success under the new prospective pricing system. The hospital's office of Case-Mix Studies has developed an accurate computer-based information system with historical, clinical, and demographic data for patients discharged from the hospital over the past five years. Reports regarding the cases, diagnoses, finances, and characteristics are shared in meetings with the hospital administration and directors of sixteen clinical departments, their staff, attending physicians, and house officers in training. The informative case-mix reports provide revealing sociodemographic summaries and have proven to be an invaluable tool for planning, marketing, and program evaluation.

  4. Enhancements to the Idaho National Engineering Laboratory motor-operated valve assessment software

    International Nuclear Information System (INIS)

    Holbrook, M.R.; Watkins, J.C.

    1994-01-01

    In January 1991, the U.S. Nuclear Regulatory Commission (USNRC) commenced Part 1 inspections to review licensee's motor-operated valve (MOV) programs that were developed to address Generic Letter 89-10, open-quotes Safety-Related Motor-Operated Valve Testing and Surveillanceclose quotes. In support, of this effort, the Isolation Valve Assessment (IVA) software, Version 3.10, was developed by the Idaho National Engineering Laboratory (INEL) to enable rapid in-depth review of MOV sizing and torque switch setting calculations. In 1994, the USNRC commenced Part 2 inspections, which involve a more in-depth review of MOV in situ testing relative to design-basis assumptions. The purpose of this paper is to describe the latest INEL and industry research that has been incorporated into Version 4.00 of the IVA software to support the latest round of inspections. Major improvements include (a) using dynamic and static test results to determine MOV performance parameters and validate design-basis engineering assumptions, (b) determining the stem/stem-nut coefficient of friction using new research-based techniques, (c) adding the ability to evaluate globe valves, and (d) incorporating new methods to account for the effects of high ambient temperature on the output torque of alternating current (ac) motors

  5. Inspection qualification programme for VVER reactors and review of round robin test results

    International Nuclear Information System (INIS)

    Horacek, L.; Zdarek, J.

    1998-01-01

    Experience obtained, especially from in-service inspections of VVER 440-type reactor pressure vessels and from the Czech round test trials with international participation of ultrasonic teams, has highlighted the need for an in-service inspection qualification programme in the Czech Republic focused on NDT procedures, equipment and personnel. Recently, several national and international regional projects included in the PHARE programme (projects 4.1.2/93 and 1.02/94), briefly described, have been initiated. These projects are to cover step by step the programme of the in-service inspection qualification in view of technical justification as well as of practical assessment-performance demonstration-for all the main VVER-type primary circuit components. (orig.)

  6. Effects of picosecond laser repetition rate on ablation of Cr12MoV cold work mold steel

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Baoye; Deng, Leimin; Liu, Peng; Zhang, Fei; Duan, Jun, E-mail: duans@hust.edu.cn; Zeng, Xiaoyan

    2017-07-01

    In this paper, the effects of pulse repetition rate on ablation efficiency and quality of Cr12MoV cold work mold steel have been studied using a picosecond (ps) pulse Nd:YVO{sub 4} laser system at λ= 1064 nm. The experimental results of area ablation on target surface reveal that laser repetition rate plays a significant role in controlling ablation efficiency and quality. Increasing the laser repetition rate, while keeping a constant mean power improves the ablation efficiency and quality. For each laser mean power, there is an optimal repetition rate to achieve a higher laser ablation efficiency with low surface roughness. A high ablation efficiency of 42.29, 44.11 and 47.52 μm{sup 3}/mJ, with surface roughness of 0.476, 0.463 and 0.706 μm could be achieved at laser repetition rate of 10 MHz, for laser mean power of 15, 17 and 19 W, respectively. Scanning electron microcopy images revels that the surface morphology evolves from rough with numerous craters, to flat without pores when we increased the laser repetition rate. The effects of laser repetition rate on the heat accumulation, plasma shield and ablation threshold were analyzed by numerical simulation, spectral analysis and multi-laser shot, respectively. The synergetic effects of laser repetition rate on laser ablation rate and machining quality were analyzed and discussed systemically in this paper.

  7. TEACHERS' VIEWS ON THE POTENTIAL USE OF ONLINE IN-SERVICE EDUCATION AND TRAINING ACTIVITIES

    Directory of Open Access Journals (Sweden)

    Mehmet KOKOC

    2011-10-01

    Full Text Available This study examined teacher’s views on the potential use of online in-service education and training (INSET activities. The study used a qualitative approach. A total of 13 in-service teachers from primary school, vocational school, science and art center, high school in Trabzon (on the Black Sea coast of Turkey participated in the study. To determine opinions of participants about the potential use of online INSET activities, a online conference was held to determine teachers’ views. The participants who had experienced traditional and face to face INSET courses discussed their INSET experiences and thoughts about online INSET activities. These views were transcribed and then analyzed using content analysis. The main conclusions are: with online INSET activities, especially time and place dependency can be overcome, and accommodation and transportation issues can be resolved. Teachers feel that online INSET activities can promote effective use of resources.

  8. Evaluation of the In-Service Education and Training Programme for Kuwait Army Instructors

    Science.gov (United States)

    Al-Mutawa, Najat; Al-Furaih, Suad

    2005-01-01

    This study evaluates the In-Service Education and Training (INSET) programme organised for Kuwait Army instructors. The focus is on their perceptual gain in related topics and skills, as they attended 10 courses at the College of Education--Kuwait University. Pre- and post-assessments involved 20 trainees. The analysis indicates significant…

  9. Alternative method of inservice hydraulic testing of difficult to test pumps

    International Nuclear Information System (INIS)

    Stockton, N.B.; Shangari, S.

    1994-01-01

    The pump test codes require that system resistance be varied until the independent variable (either the pump flow rate or differential pressure) equals its reference value. Variance from this fixed reference value is not specifically allowed. However, the design of many systems makes it impractical to set the independent variable to an exact value. Over a limited range of pump operation about the fixed reference value, linear interpolation between two points of pump operation can be used to accurately determine degradation at the reference value without repeating reference test conditions. This paper presents an overview of possible alternatives for hydraulic testing of pumps and a detailed discussion of the linear interpolation method. The approximation error associated with linear interpolation is analyzed. Methods to quantify and minimize approximation error are presented

  10. A True-False Test on Methods of Typewriting Instruction.

    Science.gov (United States)

    West, Leonard J.

    1984-01-01

    Presents a true-false test on typewriting instruction to illustrate the effects of educational lag, publishing practices, and deficiencies in preservice and inservice teacher education upon teaching methods. (SK)

  11. Crack characterization for in-service inspection planning

    International Nuclear Information System (INIS)

    Waale, J.; Ekstroem, P.

    1995-12-01

    During in-service inspection by non destructive testing the reliability is highly dependent on how the equipment is adjusted to the specific object and to the anticipated crack feature.The crack feature and morphology vary widely between different cracking mechanisms and between material types in which the cracks appear. The major objective of this study was to characterize a number of morphology parameters for common crack mechanism and structure material combinations. Critical morphology parameters are crack orientation, shape, width, surface roughness and branching. The crack parameters were evaluated from failure analyses reported from the nuclear and non-nuclear industry. In addition, a literature review was carried out on crack parameter reports and on failure analysis reports, which were further evaluated. The evaluated crack parameters were plotted and statistically processed in data groups with respect to crack mechanism and material type. The fatigue crack mechanism were classified as mechanical, thermal or corrosion fatigue and stress corrosion crack mechanism as intergranular, transgranular or inter dendritic stress corrosion cracking. Furthermore, some common weld defects were characterized for comparison. The materials were divided into three broad groups, ferritic low alloy steels, stainless steels and nickel base alloys. The results indicate significant differences between crack parameters when comparing data from different crack mechanism/material type combinations. Typical parameter values and scatter were derived for several combinations where the data was sufficient for statistical significance. 10 refs, 105 figs, 14 tabs

  12. Crack characterization for in-service inspection planning

    Energy Technology Data Exchange (ETDEWEB)

    Waale, J [SAQ Inspection Ltd, Stockholm (Sweden); Ekstroem, P [ABB Atom AB, Vaesteraas (Sweden)

    1995-12-01

    During in-service inspection by non destructive testing the reliability is highly dependent on how the equipment is adjusted to the specific object and to the anticipated crack feature.The crack feature and morphology vary widely between different cracking mechanisms and between material types in which the cracks appear. The major objective of this study was to characterize a number of morphology parameters for common crack mechanism and structure material combinations. Critical morphology parameters are crack orientation, shape, width, surface roughness and branching. The crack parameters were evaluated from failure analyses reported from the nuclear and non-nuclear industry. In addition, a literature review was carried out on crack parameter reports and on failure analysis reports, which were further evaluated. The evaluated crack parameters were plotted and statistically processed in data groups with respect to crack mechanism and material type. The fatigue crack mechanism were classified as mechanical, thermal or corrosion fatigue and stress corrosion crack mechanism as intergranular, transgranular or inter dendritic stress corrosion cracking. Furthermore, some common weld defects were characterized for comparison. The materials were divided into three broad groups, ferritic low alloy steels, stainless steels and nickel base alloys. The results indicate significant differences between crack parameters when comparing data from different crack mechanism/material type combinations. Typical parameter values and scatter were derived for several combinations where the data was sufficient for statistical significance. 10 refs, 105 figs, 14 tabs.

  13. ASME section XI - design and access requirements for in-service inspection

    International Nuclear Information System (INIS)

    Davis, D.D.

    1982-01-01

    The Owner of a nuclear power plant has the regulatory commitment to perform Section XI in-service inspection throughout the service life of a plant. In anticipation of what will be needed to perform adequately the required examinations and tests, sub-article IWA-1500 of Section XI not only requires that sufficient access be provided to accommodate equipment and inspection personnel but also requires that other provisions be considered such as: component surface preparations, material selections, shielding, removal and storage of hardware, handling equipment, and provisions for repairs and replacements. It is, therefore, the owner's and the architect engineer's responsibility to ensure that proper design and access provisions are incorporated to enable the owner to meet his commitments. Since the architect engineer usually has the prime responsibility for the implementation of design criteria, the owner must ensure that these provisions be considered in each phase of design and construction. The benefits of this can result in shorter outages, more meaningful examinations and tests and less radiation exposure of inspection personnel. This paper will address in detail those topics that affect design and access provisions which need to be considered during the design and construction of a nuclear power plant. (author)

  14. In-service inspection methods for graphite-epoxy structures on commercial transport aircraft

    Science.gov (United States)

    Phelps, M. L.

    1981-01-01

    In-service inspection methods for graphite-epoxy composite structures on commercial transport aircraft are determined. Graphite/epoxy structures, service incurred defects, current inspection practices and concerns of the airline and manufacturers, and other related information were determind by survey. Based on this information, applicable inspection nondestructive inspection methods are evaluated and inspection techniques determined. Technology is developed primarily in eddy current inspection.

  15. In-Service Training of Chemistry Teachers: The Use of Multimedia in Teaching Chemistry

    Science.gov (United States)

    Ferreira, Celeste; Baptista, Monica; Arroio, Agnaldo

    2013-01-01

    Information and Communication Technology has allowed the use of several types of visualizations, especially multimedia environments in science teaching. The aim was to investigate how in-service teachers enrolled in a training course understand the nature and the role of visualizations in science teaching as well as the impact of this training on…

  16. The Utility of the Metacognitive Awareness Inventory for Teachers among In-Service Teachers

    Science.gov (United States)

    Kallio, Heli; Virta, Kalle; Kallio, Manne; Virta, Arja; Hjardemaal, Finn Rudolf; Sandven, Jostein

    2017-01-01

    The purpose of the present study is to explore the utility of the compressed version of the Metacognitive Awareness Inventory for Teachers (MAIT-18) among in-service teachers. Knowledge of teachers' awareness of metacognition is required to support students' self-regulation, with the aim of establishing modern learning methods and life-long…

  17. The 1978 first in-service inspection of the reactor pressure vessel of the second unit of the Greifswald nuclear power plant

    International Nuclear Information System (INIS)

    Pastor, D.; Busch, R.; Hildebrandt, E.; Redlich, K.H.

    1979-01-01

    The reactor pressure vessel and the primary coolant circuit of the second 440-MW(e) unit of the Greifswald nuclear power plant were subjected to an in-service inspection. Extent of the inspection, development and construction of a reactor inspection container as well as the nondestructive materials testing methods used are described. Further, problems of performing the inspection, such as needs of time and personnel and radiation exposure, are considered. Finally, it is stated that the reactor pressure vessel was in safe operating state. (author)

  18. Proceedings of the IAEA Specialists' Meeting on experience and further improvement of in-service inspection methods and programmes of NPPs with particular emphasis on on-line techniques

    International Nuclear Information System (INIS)

    1989-01-01

    The proceedings are presented of an IAEA specialists meeting devoted to the exchange of views and experience with respect to understanding and quantifying materials ageing and degradation processes, to assessing residual life of components, to in-service materials testing, all this with the objective of improving reliability and, wherever possible, extending the useful life of nuclear power plants. (L.O.)

  19. Presentation of accessibility equipment for primary pipings, IHX, pumps and appertaining manipulator tests

    International Nuclear Information System (INIS)

    Hahn, G.; Hoeft, E.

    1980-01-01

    Accessibility and inservice procedure of SNR-300 components are described. Due to the high radiation level in the primary system it was necessary to develop special equipment to permit access to the testing components. The pertinent examination methods for surveying welding seams are acoustic (ultrasonic) and optical procedures (TV cameras, surface crack tests). This can be done by remote-controlled manipulators and special devices, which can transport the inspection system by rails to the testing position. Presently, relatively limited experience exists for such remote-controlled handling in nuclear power plants. Thus model experiments were carried out on a model pipe section at INTERATOM. The performed test shows that the concept planned to perform inservice by using remote-controlled manipulators can be realized successfully. (author)

  20. X-ray tomographic in-service inspection of girth welds - The European project TomoWELD

    International Nuclear Information System (INIS)

    Ewert, Uwe; Redmer, Bernhard; Walter, David; Thiessenhusen, Kai-Uwe; Bellon, Carsten; Nicholson, P. Ian; Clarke, Alan L.; Finke-Härkönen, Klaus-Peter

    2015-01-01

    The new standard 'ISO 17636-2:2013: Non-destructive testing of welds - Radiographic testing - Part 2: X- and gamma-ray techniques with digital detectors', defines the practice for radiographic inspection of welded pipes for manufacturing and in-service inspection. It is applied in Europe for inspections of pipe welds in nuclear power plants as well as in chemical plants and allows a faster inspection with digital detector arrays (DDA) than with film. Nevertheless, it does not allow the evaluation of the depth and shape of volumetric and planar indications. In 2001 a planar tomography scanner, TomoCAR, was introduced for mechanized radiographic testing (RT) inspection and non-destructive measurement of cross sections. The project TomoWELD is based on a new concept of the scan geometry, an enhanced GPU based reconstruction, and the application of a new generation of photon counting DDAs based on CdTe crystal CMOS hybrids. The new detector permits the selection of energy thresholds to obtain an optimum energy range and reduction of the influence of scattered radiation. The concept and first measurements are presented. Flaw depth and shape of volumetric and planar irregularities can be determined

  1. X-ray tomographic in-service inspection of girth welds - The European project TomoWELD

    Energy Technology Data Exchange (ETDEWEB)

    Ewert, Uwe, E-mail: uwe.ewert@bam.de; Redmer, Bernhard, E-mail: uwe.ewert@bam.de; Walter, David, E-mail: uwe.ewert@bam.de; Thiessenhusen, Kai-Uwe, E-mail: uwe.ewert@bam.de; Bellon, Carsten, E-mail: uwe.ewert@bam.de [BAM Bundesanstalt für Materialforschung, Berlin (Germany); Nicholson, P. Ian, E-mail: ian.nicholson@twi.co.uk [TWI Technology Centre Wales, Port Talbot (United Kingdom); Clarke, Alan L. [TWI Technology Centre Wales, Port Talbot (United Kingdom); Finke-Härkönen, Klaus-Peter, E-mail: klaus.harkonen@ajat.fi [Oy AJAT Ltd., Helsinki (Finland)

    2015-03-31

    The new standard 'ISO 17636-2:2013: Non-destructive testing of welds - Radiographic testing - Part 2: X- and gamma-ray techniques with digital detectors', defines the practice for radiographic inspection of welded pipes for manufacturing and in-service inspection. It is applied in Europe for inspections of pipe welds in nuclear power plants as well as in chemical plants and allows a faster inspection with digital detector arrays (DDA) than with film. Nevertheless, it does not allow the evaluation of the depth and shape of volumetric and planar indications. In 2001 a planar tomography scanner, TomoCAR, was introduced for mechanized radiographic testing (RT) inspection and non-destructive measurement of cross sections. The project TomoWELD is based on a new concept of the scan geometry, an enhanced GPU based reconstruction, and the application of a new generation of photon counting DDAs based on CdTe crystal CMOS hybrids. The new detector permits the selection of energy thresholds to obtain an optimum energy range and reduction of the influence of scattered radiation. The concept and first measurements are presented. Flaw depth and shape of volumetric and planar irregularities can be determined.

  2. In-service crosstalk monitoring for dense space division multiplexed multi-core fiber transmission systems

    DEFF Research Database (Denmark)

    Mizuno, T.; Isoda, A.; Shibahara, K.

    2017-01-01

    We present in-service inter-core crosstalk monitoring for MCF transmission systems. We transmit 54-WDM PDM-16QAM signals over 111.6-km 32-core DSDM transmission line incorporating cladding-pumped 32-core MC-EYDFA, and demonstrate -30 dB crosstalk monitoring without affecting transmission...

  3. Why Change to Active Learning? Pre-Service and In-Service Science Teachers' Perceptions

    Science.gov (United States)

    O'Grady, Audrey; Simmie, Geraldine Mooney; Kennedy, Therese

    2014-01-01

    This article explores pre-service and in-service science teachers' perceptions on active learning, and examines the effectiveness of active learning by pre-service science teachers in the Irish second level classroom through a two-phase study. In the first phase, data on perceptions were gathered from final year pre-service teachers and in-service…

  4. Nuclear containment systems and in-service inspection status of Korea nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jihong, Park; Jaekeun, Hong; Banuk, Park [Korea Institute of Machinery and Materials, Dept. of Authorized Test and Evaluation, Kyungnam (Korea, Republic of)

    2007-07-01

    20 unit nuclear power plants in Korea have been operated and maintained since the first unit started in commercial service in 1978. Most recently 4 units were under construction and several units were planned to be constructed. by industries. 4 types of nuclear containment systems have been constructed until now: first, metal containments, then pre-stressed concrete containments with grouted tendon systems, followed by pre-stressed concrete containments with un-grouted tendon systems, and Korea standard nuclear containments. All the nuclear containments should be inspected periodically. Therefore for periodic in-service inspection, several appropriate technical requirements should be applied differently depending on the specific nuclear containment types. With the changes of times, nuclear containment systems have undergone a remarkable change, and finally nuclear containment system of Korea standard nuclear power plant was settled down, and as a matter of course it dominates the trend of present and future nuclear containment systems. Overall in-service inspection results of most Korea nuclear containments have not showed any serious evidence of degradation.

  5. Analysis of pre-service and in-service views of evolution of Serbian teachers

    Directory of Open Access Journals (Sweden)

    Stanisavljević Jelena

    2015-01-01

    Full Text Available We analysed the potential differences between the conceptions of Serbian pre-service and in-service teachers using controlled parameters such as acceptance of the evolution theory. Our sample includes Primary School teachers as well as Secondary School teachers of Biology and of Language. We show that the ideas of pre-service (PreB and in-service biology teachers (InB are more evolutionary than those of their colleagues. In contrast, most creationist responses came from the groups of pre-service language (PreL and pre-service primary teachers (PreP. The agnostic teachers are more evolutionist than other teachers. The more a teacher believes in God and practices religion, the more creationist he or she is, but a great number of teachers who believe in God are evolutionist or simultaneously evolutionist and creationist. There is a positive correlation between evolutionist answers and the attitude that „Science and religion should be separated“, and „religion and politics should be separated“. [Projekat Ministarstva nauke Republike Srbije, br. 173038 i br. III 43001

  6. MIR: an in-service inspection device for Superphenix 1 vessels

    International Nuclear Information System (INIS)

    Asty, M.; Ceccato, S.; Lerat, B.; Viard, J.

    1986-06-01

    The main and safety vessels of SUPERPHENIX 1 were designed to allow in-service inspections. The remote controlled inspection device MIR was developed for this purpose. It allows both visual and ultrasonic examinations to be performed. Basically, MIR consists of a tetrahedral structure provided with four steering and traction wheels, two for each vessel. A computer assisted control system enables it to be driven to any position on either the main or safety vessels. Operating conditions are briefly reviewed and the main features of MIR presented

  7. An evaluation of human factors research for ultrasonic inservice inspection

    International Nuclear Information System (INIS)

    Pond, D.J.; Donohoo, D.T.; Harris, R.V. Jr.

    1998-03-01

    This work was undertaken to determine if human factors research has yielded information applicable to upgrading requirements in ASME Boiler and Pressure Vessel Code Section XI, improving methods and techniques in Section V, and/or suggesting relevant research. A preference was established for information and recommendations which have become accepted and standard practice. Manual Ultrasonic Testing/Inservice Inspection (UT/ISI) is a complex task subject to influence by dozens of variables. This review frequently revealed equivocal findings regarding effects of environmental variables as well as repeated indications that inspection performance may be more, and more reliably, influenced by the workers' social environment, including managerial practices, than by other situational variables. Also of significance are each inspector's relevant knowledge, skills, and abilities, and determination of these is seen as a necessary first step in upgrading requirements, methods, and techniques as well as in focusing research in support of such programs, While understanding the effects and mediating mechanisms of the variables impacting inspection performance is a worthwhile pursuit for researchers, initial improvements in industrial UTASI performance may be achieved by implementing practices already known to mitigate the effects of potentially adverse conditions. 52 refs., 2 tabs

  8. An evaluation of human factors research for ultrasonic inservice inspection

    Energy Technology Data Exchange (ETDEWEB)

    Pond, D.J.; Donohoo, D.T.; Harris, R.V. Jr.

    1998-03-01

    This work was undertaken to determine if human factors research has yielded information applicable to upgrading requirements in ASME Boiler and Pressure Vessel Code Section XI, improving methods and techniques in Section V, and/or suggesting relevant research. A preference was established for information and recommendations which have become accepted and standard practice. Manual Ultrasonic Testing/Inservice Inspection (UT/ISI) is a complex task subject to influence by dozens of variables. This review frequently revealed equivocal findings regarding effects of environmental variables as well as repeated indications that inspection performance may be more, and more reliably, influenced by the workers` social environment, including managerial practices, than by other situational variables. Also of significance are each inspector`s relevant knowledge, skills, and abilities, and determination of these is seen as a necessary first step in upgrading requirements, methods, and techniques as well as in focusing research in support of such programs, While understanding the effects and mediating mechanisms of the variables impacting inspection performance is a worthwhile pursuit for researchers, initial improvements in industrial UTASI performance may be achieved by implementing practices already known to mitigate the effects of potentially adverse conditions. 52 refs., 2 tabs.

  9. Investigating the Information Technology Courses for Pre-service and In-service English Teachers in Hong Kong

    Directory of Open Access Journals (Sweden)

    Chi Cheung Ruby Yang

    2011-07-01

    Full Text Available This paper focuses on the views of twenty-six pre-service and eight in-service English teachers in Hong Kong concerning the information technology courses in their teacher education programmes. The findings of the study show that while both software applications and technological integration in teaching are highlighted in the course outline, the instructor focused more on the application aspect, with the technology integration being less emphasised. Another important finding is that PowerPoint was still the most commonly used application in teaching. Likewise, usually the involved pre-service and in-service teachers just simply used different computer applications as alternatives to traditional teaching resources. This may reflect the fact that the information technology courses are not adequate to prepare teachers to teach with it.

  10. Light water reactor pressure isolation valve performance testing

    International Nuclear Information System (INIS)

    Neely, H.H.; Jeanmougin, N.M.; Corugedo, J.J.

    1990-07-01

    The Light Water Reactor Valve Performance Testing Program was initiated by the NRC to evaluate leakage as an indication of valve condition, provide input to Section XI of the ASME Code, evaluate emission monitoring for condition and degradation and in-service inspection techniques. Six typical check and gate valves were purchased for testing at typical plant conditions (550F at 2250 psig) for an assumed number of cycles for a 40-year plant lifetime. Tests revealed that there were variances between the test results and the present statement of the Code; however, the testing was not conclusive. The life cycle tests showed that high tech acoustic emission can be utilized to trend small leaks, that specific motor signature measurement on gate valves can trend and indicate potential failure, and that in-service inspection techniques for check valves was shown to be both feasible and an excellent preventive maintenance indicator. Life cycle testing performed here did not cause large valve leakage typical of some plant operation. Other testing is required to fully understand the implication of these results and the required program to fully implement them. (author)

  11. In-Service Science Teachers' and the Use of Multimedia as a Teaching Tool

    Science.gov (United States)

    Ameyaw, Y.; Quansah, E.

    2013-01-01

    The study investigated the attitudes of in-service teachers' towards the use of multimedia as a tool for science teaching in Junior High Schools in the Greater Accra Region of Ghana. The population sample consisted of 100 Junior High School (JHS) science teachers made up of 60 urban teachers and 40 rural teachers from three selected districts…

  12. Metaphors as Two-Way Mirrors: Illuminating Preservice to In-Service Teacher Identity Development

    Science.gov (United States)

    Buchanan, John

    2015-01-01

    The transition from pre-service to in-service can be difficult for teachers. One means of looking into the minds and hearts of such teachers is to elicit the metaphors they adopt for themselves. Previous studies have indicated that during this transition much of the confidence, idealism and optimism of teacher metaphors is displaced by bleak and…

  13. Community of Inquiry Development in a Blended Learning Course for In-Service Teachers

    Science.gov (United States)

    Theodosiadou, Dimitra; Konstantinidis, Angelos; Pappos, Christos; Papadopoulos, Nikos

    2017-01-01

    The paper presents the course design and evaluation methods of an online community of inquiry that is developed in a blended learning training course for in-service teachers working in public K-6 schools in Greece. The course content is about digital storytelling, its educational value, and the use of supportive web 2.0 tools for developing…

  14. Development of an Online Exoplanet Course for In-Service Teachers

    Science.gov (United States)

    Barringer, Daniel; Palma, Christopher

    2016-01-01

    The Earth and Space Science Partnership (ESSP) is a collaboration among Penn State scientists, science educators and seven school districts across Pennsylvania. Penn State also offers through its fully online World Campus the opportunity for In-Service science teachers to earn an M.Ed. degree in Earth Science, and we currently offer a required online astronomy course for that program. We have previously presented descriptions of how have incorporated research-based pedagogical practices into ESSP-sponsored workshops for in-service teachers (Palma et al. 2013) and into a pilot section of introductory astronomy for non-science majors (Palma et al. 2014). In this presentation, we detail the design and development of a new online astronomy course to be offered through the M.Ed. Earth Science degree program. This course also uses a coherent content storyline approach (Roth et al. 2011), and will engage the teachers in investigations using authentic data within the Claims Evidence Reasoning framework (McNeill & Krajcik 2012). The course theme will be exploring exoplanets in order to show how these objects have forced us to reconsider some ideas in our model for the formation of the Solar System, which is a disciplinary core idea identified in the Next Generation Science Standards (citation). Course materials will be made available through Penn State's open courseware initiative and will be promoted to teachers throughout PA through the Pennsylvania Earth Science Teachers' Association (PAESTA). We gratefully acknowledge support from the NSF MSP program award DUE#0962792.

  15. Automated ultrasonic testing--capabilities, limitations and methods

    International Nuclear Information System (INIS)

    Beller, L.S.; Mikesell, C.R.

    1977-01-01

    The requirements for precision and reproducibility of ultrasonic testing during inservice inspection of nuclear reactors are both quantitatively and qualitatively more severe than most current practice in the field can provide. An automated ultrasonic testing (AUT) system, which provides a significant advancement in field examination capabilities, is described. Properties of the system, its application, and typical results are discussed

  16. Improving Teachers' In-Service Professional Development in Mathematics and Science: The Role of Postsecondary Institutions.

    Science.gov (United States)

    Desimone Laura; Garet, Michael S.; Birman, Beatrice F.; Porter, Andrew; Yoon, Kwang Suk

    2003-01-01

    As part of national evaluation of Eisenhower Professional Development Program, examines management and implementation strategies contributing to high-quality inservice teacher professional development in mathematics and science. Finds higher quality professional development is related to management and implementation strategies such as continuous…

  17. Snapshots of Authentic Scientific Inquiry and Teacher Preparation: Undergraduate STEM Courses, Preservice and Inservice Teachers' Experiences

    Science.gov (United States)

    French, Debbie Ann

    In this dissertation, the researcher describes authentic scientific inquiry (ASI) within three stages of teacher preparation and development: a1) undergraduate STEM courses, b2) preservice secondary science education methods courses, and c3) inservice teacher professional development (PD). Incorporating (ASI)-- pedagogy closely modeling the research practices of scientists--is at the forefront of national science, technology, engineering, and mathematics (STEM) initiatives and the Next Generation Science Standards (NGSS). In the first of three research articles, 42 students participated in an introductory astronomy course which employed inquiry-based pedagogy. The researcher administered the Test Of Astronomy STandards (TOAST) pre/post instruction. In the second article, 56 preservice secondary science teachers completed ideal lesson plan scenarios before and after 80 hours of methods instruction. The researcher scored the scenarios using a rubrirubric developedc according to the NGSS Science and Engineering Practices, and analyzed the components from the scenarios. The third article surveyed 63 inservice STEM teachers with prior research and industry experience. The researcher highlights teacher ASI perspectives. Overall, teachers incorporated opportunities for K-20 students to use scientific instrumentation and technology to collect and analyze data, work collaboratively, and develop evidence-based conclusions. Few teachers provided opportunities for students to ask scientific questions or disseminate results, suggesting the need that teachers (at all levels) need scaffolded instruction in these areas. The researcher argues that while ASI and STEM PDs are effective for teachers, developing similar interest, on-going communities of practice may provide support for teacher to implement the ASI practices in their classrooms.

  18. Introduction of the human proα1(I) collagen gene into proα1(I)-deficient Mov-13 mouse cells leads to formation of functional mouse-human hybrid type I collagen

    International Nuclear Information System (INIS)

    Schnieke, A.; Dziadek, M.; Bateman, J.; Mascara, T.; Harbers, K.; Gelinas, R.; Jaenisch, R.

    1987-01-01

    The Mov-13 mouse strain carries a retroviral insertion in the proα1(I) collagen gene that prevents transcription of the gene. Cell lines derived from homozygous embryos do not express type I collagen although normal amounts of proα2 mRNA are synthesized. The authors have introduced genomic clones of either the human or mouse proα1(I) collagen gene into homozygous cell lines to assess whether the human or mouse proα1(I) chains can associate with the endogenous mouse proα2(I) chain to form stable type I collagen. The human gene under control of the simian virus 40 promoter was efficiently transcribed in the transfected cells. Protein analyses revealed that stable heterotrimers consisting of two human α1 chains and one mouse α2 chain were formed and that type I collagen was secreted by the transfected cells at normal rates. However, the electrophoretic migration of both α1(I) and α2(I) chains in the human-mouse hybrid molecules were retarded, compared to the α(I) chains in control mouse cells. Inhibition of the posttranslational hydroxylation of lysine and proline resulted in comigration of human and mouse α1 and α2 chains, suggesting that increased posttranslational modification caused the altered electrophoretic migration in the human-mouse hybrid molecules. Amino acid sequence differences between the mouse and human α chains may interfere with the normal rate of helix formation and increase the degree of posttranslational modifications similar to those observed in patients with lethal perinatal osteogenesis imperfecta. The Mov-13 mouse system should allow the authors to study the effect specific mutations introduced in transfected proα1(I) genes have on the synthesis, assembly, and function of collagen I

  19. The influence of frequency and reliability of in-service inspection on reactor pressure vessel disruptive failure probability

    International Nuclear Information System (INIS)

    Jordan, G.M.

    1978-01-01

    A simple probabilistic methodology is used to investigate the benefit, in terms of reduction of disruptive failure probability, which comes from the application of periodic in-service inspection to nuclear pressure vessels. The analysis indicates the strong interaction between inspection benefit and the intrinsic quality of the structure. In order to quantify the inspection benefit, assumptions are made which allow the quality to be characterised in terms of the parameters governing a log normal distribution of time - to - failure. Using these assumptions, it is shown that the overall benefit of in-service inspection unlikely to exceed an order of magnitude in terms of reduction of disruptive failure probability. The method is extended to evaluate the effect of the periodicity and reliability of the inspection process itself. (author)

  20. Proposals for in-service inspection and monitoring of selected components located within or part of the primary containment of sodium cooled fast reactors

    International Nuclear Information System (INIS)

    Bolt, P.R.

    1976-01-01

    Design and operational experience of CEGB gas cooled reactors and certain overseas reactor plant is reviewed in relation to in-service inspection and monitoring capabilities. Design guidelines and preliminary proposals are given for in-service inspection and monitoring of selected components located within or part of the primary containment of sodium cooled fast reactors. Specific comments are made on the items of further design and development work believed to be necessary

  1. On the approximation of crack shapes found during inservice inspection

    International Nuclear Information System (INIS)

    Bhate, S.R.; Chawla, D.S.; Kushwaha, H.S.

    1997-01-01

    This paper addresses the characterization of axial internal flaw found during inservice inspection of a pipe. J-integral distribution for various flaw shapes is obtained using line spring finite, element method. The peak J-value and its distribution across the crack is found to be characteristic feature of each shape. The triangular shape yields peak J-value away from the center, the point of depth. The elliptic approximation results in large overestimate of J-value for unsymmetric flaws. Triangular approximation is recommended for such flaws so that further service can be obtained from the component

  2. On the approximation of crack shapes found during inservice inspection

    Energy Technology Data Exchange (ETDEWEB)

    Bhate, S.R.; Chawla, D.S.; Kushwaha, H.S. [Bhabha Atomic Research Centre, Bombay (India)] [and others

    1997-04-01

    This paper addresses the characterization of axial internal flaw found during inservice inspection of a pipe. J-integral distribution for various flaw shapes is obtained using line spring finite, element method. The peak J-value and its distribution across the crack is found to be characteristic feature of each shape. The triangular shape yields peak J-value away from the center, the point of depth. The elliptic approximation results in large overestimate of J-value for unsymmetric flaws. Triangular approximation is recommended for such flaws so that further service can be obtained from the component.

  3. Effectiveness of an Alternative Delivery System for In-Service Vocational Teacher Education. Final Report.

    Science.gov (United States)

    Richardson, Donald L.; And Others

    The project was designed to provide vocational teacher educators in Colorado with an alternative delivery system for inservice vocational teacher education which would overcome barriers of distance (and difficult winter travel), expense, and low student density. A task force composed of staff members of the State Board for Community Colleges and…

  4. In-service and Pre-service Middle School Mathematics Teachers' Attitudes and Decisions Regarding Teaching Mathematics Using Mobile Phones

    Directory of Open Access Journals (Sweden)

    Wajeeh M. Daher

    2014-10-01

    Full Text Available Several researches examined students' mathematics learning using mobile phones, while very few researches examined mathematics teaching using this new educational tool. This research attempts to analyze in-service and pre-service teachers' attitudes and decisions regarding mathematics teaching with mobile phones using activity theory. More specifically, three case studies are analyzed in this research: One concerns an in-service teacher who used mobile phones in her class, the second case study involves a pre-service teacher who collaborated with the in-service teacher to teach mathematics lessons using mobile phones, and the third case study is about 15 pre-service teachers who were observers of the experiment but did not use mobile phones in their teaching. We held one-hour semi-structured interviews with the in-service teacher, with the leading pre-service teacher and with the group of other observer pre-service teachers. This happened three times during the academic year: at the beginning of the experiment, after three months and after it ended. The research findings indicate that different factors have an impact on the attitudes and decisions of the teacher: history of the teacher using technologies in teaching, perceptions of the teacher using technologies in teaching, community’s teacher, rules regulating the use of technologies in teaching mathematics, and division of labor. For example, questions as to who decides which technologies to use in the classroom and who should prepare the learning material for the students. Contradictions were identified in mathematics teachers' activity when utilizing mobile phones in their teaching. These contradictions hinder or slow such utilization. Community, especially its leading members, mediated and helped overcome the activity contradictions that arose throughout the experiment regarding the teaching processes in and/or out of the mathematics classroom.

  5. The Iowa K-12 Climate Science Education Initiative: a comprehensive approach to meeting in-service teachers' stated needs for teaching climate literacy with NGSS

    Science.gov (United States)

    Stanier, C. O.; Spak, S.; Neal, T. A.; Herder, S.; Malek, A.; Miller, Z.

    2017-12-01

    The Iowa Board of Education voted unanimously in 2015 to adopt NGSS performance standards. The CGRER - College of Education Iowa K-12 Climate Science Education Initiative was established in 2016 to work directly with Iowa inservice teachers to provide what teachers need most to teach climate literacy and climate science content through investigational learning aligned with NGSS. Here we present teachers' requests for teaching climate with NGSS, and an approach to provide resources for place-based authentic inquiry on climate, developed, tested, and refined in partnership with inservice and preservice teachers. A survey of inservice middle school and high school science teachers was conducted at the 2016 Iowa Council of Teachers of Mathematics/Iowa Academy of Sciences - Iowa Science Teaching Section Fall Conference and online in fall 2016. Participants (n=383) were asked about their prior experience and education, the resources they use and need, their level of comfort in teaching climate science, perceived barriers, and how they address potential controversy. Teachers indicated preference for professional development on climate content and complete curricula packaged with lessons and interactive models aligned to Iowa standards, as well as training on instructional strategies to enhance students' ability to interpret scientific evidence. We identify trends in responses by teaching experience, climate content knowledge and its source, grade level, and urban and rural districts. Less than 20% of respondents reported controversy or negativity in teaching climate to date, and a majority were comfortable teaching climate science and climate change, with equal confidence in teaching climate and other STEM content through investigational activities. We present an approach and materials to meet these stated needs, created and tested in collaboration with Iowa teachers. We combine professional development and modular curricula with bundled standards, concepts, models, data

  6. Analysis of References on the Plastic Surgery In-Service Training Exam.

    Science.gov (United States)

    Silvestre, Jason; Zhang, Alicia; Lin, Samuel J

    2016-06-01

    The Plastic Surgery In-Service Training Exam is a knowledge assessment tool widely used during plastic surgery training in the United States. This study analyzed literature supporting correct answer choices to determine highest yield sources, journal publication lag, and journal impact factors. Digital syllabi of 10 consecutive Plastic Surgery In-Service Training Exam administrations (2006 to 2015) were reviewed. The most-referenced articles, journals, and textbooks were determined. Mean journal impact factor and publication lag were calculated and differences were elucidated by section. Two thousand questions and 5386 references were analyzed. From 2006 to 2015, the percentage of journal citations increased, whereas textbook references decreased (p < 0.001). Plastic and Reconstructive Surgery was cited with greatest frequency (38.5 percent), followed by Clinics in Plastic Surgery (5.6 percent), Journal of Hand Surgery (American volume) (5.1 percent), and Annals of Plastic Surgery (3.8 percent). There was a trend toward less publication lag over the study period (p = 0.05), with a mean publication lag of 9.1 ± 9.0 years for all journal articles. Mean journal impact factor was 2.3 ± 4.3 and lowest for the hand and lower extremity section (1.7 ± 2.8; p < 0.001). The highest yield textbooks were elucidated by section. Plastic surgery faculty and residents may use these data to facilitate knowledge acquisition during residency.

  7. The effect of in-service entrepreneurship training on mass media managers’ entrepreneurship: A case study of IRIB

    Directory of Open Access Journals (Sweden)

    Hassan Motaharrad

    2014-12-01

    Full Text Available This study investigates the impact of in-service entrepreneurship training on the improvement of mass media managers’ entrepreneurship in Islamic Republic of Iran Broadcasting (IRIB, Tehran, Iran. Features of corporate entrepreneurship were regarded as four dimensions of creativity and innovation, risk-taking, perseverance, and competitive spirit. Also, we examined the effect of entrepreneurship training on corporate entrepreneurship. To collect the data, we developed a questionnaire. Forty four production managers of IRIB volunteered to fill in the questionnaire. However, 4 persons were excluded from the group due to incomplete completion of the questionnaire and treatment which made the participants 40 people. The participants were randomly assigned to two participating groups. To test the hypotheses, variance and multi-covariance tests were applied. The analysis of the data obtained showed that the entrepreneurship training has significant effect on creativity, risk-taking, perseverance, and competitive spirit.

  8. Greek In-Service and Preservice Teachers' Views about Bullying in Early Childhood Settings

    Science.gov (United States)

    Psalti, Anastasia

    2017-01-01

    Despite the plethora of studies regarding bullying worldwide, there are limited studies at the early childhood level. This article presents the results of a pilot study aiming at exploring preservice and in-service early childhood teachers' views on bullying in Greek early childhood settings. A total of 192 early childhood teachers completed a…

  9. Using In-Service and Coaching to Increase Teachers' Accurate Use of Research-Based Strategies

    Science.gov (United States)

    Kretlow, Allison G.; Cooke, Nancy L.; Wood, Charles L.

    2012-01-01

    Increasing the accurate use of research-based practices in classrooms is a critical issue. Professional development is one of the most practical ways to provide practicing teachers with training related to research-based practices. This study examined the effects of in-service plus follow-up coaching on first grade teachers' accurate delivery of…

  10. Development of in-service inspection plans for nuclear components at the Surry 1 nuclear power station

    International Nuclear Information System (INIS)

    Vo, T.V.; Simonen, F.A.; Doctor, S.R.; Smith, B.W.; Gore, B.F.

    1993-01-01

    As part of the nondestructive evaluation reliability program sponsored by the US Nuclear Regulatory Commission at Pacific Northwest Laboratory, a methodology has been developed for establishing in-service inspection priorities of nuclear power plant components. The method uses results of probabilistic risk assessment in conjunction with the techniques of failure modes and effects analysis to identify and prioritize the most risk-important systems and components for inspection at nuclear power plants. Surry nuclear power station unit 1 was selected for demonstrating the methodology. The specific systems selected for analysis were the reactor pressure vessel, the reactor coolant, the low pressure injection including the accumulators, and the auxiliary feedwater. The results provide a risk-based ranking of components that can be used to establish a prioritization of the components and a basis for developing improved in-service inspection plans at nuclear power plants

  11. An automated eddy current in-service inspection system for nuclear steam generator tubing

    International Nuclear Information System (INIS)

    Wells, N.S.

    1981-06-01

    A prototype steam generator in-service inspection system incorporating remotely-controlled instrumentation linked by a digital transmission line to an instrument and control trailer outside the reactor containment has been designed and manufactured and is presently undergoing field tests. The (Monel 400) steam generator tubes are scanned two at a time using absolute eddy current probes controlled by two remotely-operated probe drives at a scanning speed of 0.5 m/s. The probes are positioned on the tubesheet by a light-weight (1.5 kg) microprocessor-operated tubesheet walker mechanism. Digitized control and data signals are transmitted up to 300 m to the control trailer. There the control and analysis computers extract the relevant signal information and present it in condensed form as labelled graphics on CRT consoles for on-line visual assessment. Hard copy output is also provided for each tube scanned (one per minute). Condensed data is archived on magnetic tapes for additional off-line analysis and comparisons with other inspections

  12. Confrontation (A Human Relations Training Unit and Simulation Game for Teacher and Administrators in a Multi-Ethnic Elementary and High School). Description of Teacher Inservice Education Materials.

    Science.gov (United States)

    National Education Association, Washington, DC. Project on Utilization of Inservice Education R & D Outcomes.

    The inservice teacher and administrator education program described here is intended to make teachers aware of the problems they may encounter in a multicultural, multiethnic school setting. The inservice topic is human relations, with the subject of black/white confrontation the main focus. This descriptive report provides additional information…

  13. Evaluation and improvement in nondestructive examination (NDE) reliability for inservice inspection of light water reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Deffenbaugh, J.D.; Good, M.S.; Green, E.R.; Heasler, P.G.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.

    1988-01-01

    The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) program at the Pacific Northwest Laboratory was established by the NRC to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements, based on material properties, service conditions and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other inspected components. This is a progress report covering the programmatic work from October 1986 through September 1987. (author)

  14. Evaluation and improvement in nondestructive examination (NDE) reliability for inservice inspection of light water reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Deffenbaugh, J.D.; Good, M.S.; Green, E.R.; Heasler, P.G.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.

    1988-01-01

    The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactor (NDE Reliability) program at the Pacific Northwest Laboratory was established by the NRC to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other inspected components. This is a progress report covering the programmatic work from October 1986 through September 1987

  15. Preservice and Inservice Teachers' Challenges in the Planning of Practical Work in Physics

    Science.gov (United States)

    Nivalainen, Ville; Asikainen, Mervi A.; Sormunen, Kari; Hirvonen, Pekka E.

    2010-06-01

    Practical work in school science plays many essential roles that have been discussed in the literature. However, less attention has been paid to how teachers learn the different roles of practical work and to the kind of challenges they face in their learning during laboratory courses designed for teachers. In the present study we applied the principles of grounded theory to frame a set of factors that seem to set major challenges concerning both successful work in the school physics laboratory and also in the preparation of lessons that exploit practical work. The subject groups of the study were preservice and inservice physics teachers who participated in a school laboratory course. Our results derived from a detailed analysis of tutoring discussions between the instructor and the participants in the course, which revealed that the challenges in practical or laboratory work consisted of the limitations of the laboratory facilities, an insufficient knowledge of physics, problems in understanding instructional approaches, and the general organization of practical work. Based on these findings, we present our recommendations on the preparation of preservice and inservice teachers for the more effective use of practical work in school science and in school physics.

  16. Psychometric properties of the Turkish adaptation of the Mathematics Teacher Efficacy Belief Instrument for in-service teachers.

    Science.gov (United States)

    Cetinkaya, Bulent; Erbas, Ayhan Kursat

    2011-11-01

    Teaching efficacy beliefs have attracted researchers' attention in recent decades because of its close association with and potential impact on the implementation of new ideas and skills in education. In the present study, we have explored the psychometric properties and construct validity of the Turkish adaptation of the Mathematics Teacher Efficacy Belief Instrument developed by Enochs, Smith, & Huinker (2000) for in-service mathematics teachers. The instrument distinguishes between two dimensions of efficacy beliefs for mathematics teachers: personal mathematics teaching efficacy and mathematics teaching outcome expectancy. The sample consisted of 1355 in-service elementary school teachers and middle school mathematics teachers from 368 schools. Exploratory and confirmatory factor analysis revealed a two-factor structure similar to that found in other studies. Also, scores from the two subscales indicated acceptable internal consistency.

  17. Using Innovative Resources and Programs to Prepare Pre- and In-Service Teachers for New Science Standards

    Science.gov (United States)

    Kinzler, R. J.; Short, J.; Contino, J.; Cooke-Nieves, N.; Howes, E.; Kravitz, D.; Randle, D.; Trowbridge, C.

    2014-12-01

    Leveraging the Rose Center for Earth and Space and active research departments in Earth and Planetary Science, Astrophysics, and Paleontology, the Education Department at the American Museum of Natural History (AMNH) offers an MAT program to prepare new Earth Science teachers (~100 new teachers by 2018) as well as a range of professional development (PD) opportunities for over 3,000 K-12 teachers annually, providing opportunities to learn with scientists; inquiry-based experiences; and standards-aligned resources. The AMNH produces innovative geoscience and other STEM resources supporting teacher and student science investigations with data visualizations and analysis tools, teaching case materials and other resources that provide rich nonfiction reading and writing opportunities for use in Earth and space science curricula that are integrated in the MAT and PD programs. Museum resources and the MAT and PD programs are aligned to support the recently released Next Generation Science Standards (NGSS) and the Common Core State Standards. The NGSS is a set of science and engineering practices, crosscutting concepts and disciplinary core ideas to help cultivate teachers' and K-12 students' scientific habits of mind, develop their knowledge and abilities to engage in scientific investigations, and teach them how to reason in context; goals that closely align with those of the AMNH's teacher preparation and professional development programs. A Framework for K-12 Science Education: Practices, Crosscutting Concepts, and Core Ideas (NRC, 2012) is a required text for the MAT program, and this text as well as the NGSS Performance Expectations guide the PD programs as well. Researchers working with Museum scientists and educators find it is not enough for programs for pre- and in-service teachers to provide access to resources. Research suggests that these programs need to engage pre- and in-service teachers in using and reflecting on these types of resources, as well as take

  18. Remote controlled ultrasonic pre-service and in-service inspections of reactor pressure vessels

    International Nuclear Information System (INIS)

    Mueller, G.

    1990-01-01

    The first mechanised in-service inspection of the reactor pressure vessel on unit one of Eskom's Koeberg nuclear power station has been carried out. Since 1968 a whole range of manipulators to carry out remote controlled ultrasonic inspections of nuclear power station equipment has been developed. The inspection of a reactor pressure vessel using a central mast manipulator is described. 3 figs., 1 ill

  19. Diatom community structure on in-service cruise ship hulls.

    Science.gov (United States)

    Hunsucker, Kelli Zargiel; Koka, Abhishek; Lund, Geir; Swain, Geoffrey

    2014-10-01

    Diatoms are an important component of marine biofilms found on ship hulls. However, there are only a few published studies that describe the presence and abundance of diatoms on ships, and none that relate to modern ship hull coatings. This study investigated the diatom community structure on two in-service cruise ships with the same cruise cycles, one coated with an antifouling (AF) system (copper self-polishing copolymer) and the other coated with a silicone fouling-release (FR) system. Biofilm samples were collected during dry docking from representative areas of the ship and these provided information on the horizontal and vertical zonation of the hull, and intact and damaged coating and niche areas. Diatoms from the genera Achnanthes, Amphora and Navicula were the most common, regardless of horizontal ship zonation and coating type. Other genera were abundant, but their presence was more dependent on the ship zonation and coating type. Samples collected from damaged areas of the hull coating had a similar community composition to undamaged areas, but with higher diatom abundance. Diatom fouling on the niche areas differed from that of the surrounding ship hull and paralleled previous studies that investigated differences in diatom community structure on static and dynamically exposed coatings; niche areas were similar to static immersion and the hull to dynamic immersion. Additionally, diatom richness was greater on the ship with the FR coating, including the identification of several new genera to the biofouling literature, viz. Lampriscus and Thalassiophysa. These results are the first to describe diatom community composition on in-service ship hulls coated with a FR system. This class of coatings appears to have a larger diatom community compared to copper-based AF systems, with new diatom genera that have the ability to stick to ship hulls and withstand hydrodynamic forces, thus creating the potential for new problematic species in the biofilm.

  20. The influences of impurity content, tensile strength, and grain size on in-service temper embrittlement of CrMoV steels

    International Nuclear Information System (INIS)

    Cheruvu, N.S.; Seth, B.B.

    1989-01-01

    The influences of impurity levels, grain size, and tensile strength on in-service temper embrittlement of CrMoV steels have been investigated. The samples for this study were taken from steam turbine CrMoV rotors which had operated for 15 to 26 years. The effects of grain size and tensile strength on embrittlement susceptibility were separated by evaluating the embrittlement behavior of two rotor forgings made from the same ingot after an extended step-cooling treatment. Among the residual elements in the steels, only P produces a significant embrittlement. The variation of P and tensile strength has no effect on in-service temper embrittlement susceptibility, as measured by the shift in fracture appearance transition temperature (FATT). However, the prior austenite grain size plays a major role in service embrittlement. The fine grain steels with a grain size of ASTM No. 9 or higher are virtually immune to in-service embrittlement. In steels having duplex grain sizes, embrittlement susceptibility is controlled by the size of coarser grains. For a given steel chemistry, the coarse grain steel is more susceptible to in-service embrittlement, and a decrease in ASTM grain size number from 4 to 0/1 increases the shift in FATT by 61 degrees C (10/10 degrees F). It is demonstrated that long-term service embrittlement can be simulated, except in very coarse grain steels, by using the extended step-cooling treatment. The results of step-cooling studies show that the coarse grain rotor steels take longer time during service to reach a fully embrittled state than the fine grain rotor steels

  1. University-School Partnerships: Pre-Service and In-Service Teachers Working Together to Teach Primary Science

    Science.gov (United States)

    Kenny, John Daniel

    2012-01-01

    This paper reports on a partnership approach preparing pre-service primary teachers to teach science. Partnerships involving pre-service teachers and volunteer in-service colleagues were formed to teach science in the classroom of the colleague, with support from the science education lecturer. Each pre-service teacher collaboratively planned and…

  2. Developments for the ultrasonic in-service inspection of the inner near surface zone of circular welds in the vessel of the fast breeder-reactor SNR 300

    International Nuclear Information System (INIS)

    Salzburger, H.J.; Huebschen, G.; Neuschwander, R.; Kleffner, G.; Wessels, J.

    1990-01-01

    For in-service, ultrasonic inspection of the inner near-surface zone of the welds 1 and 6 of the vessel of the SNR-300, an automated system has been developed for scanning, manipulation and evaluation tasks. The scanning system which currently is tested and qualified as a prototype system uses heat-resistant EMUS probes which do not require coupling agents, and which have been optimized for three different testing tasks. The required electronic equipment has also been developed to prototype stage, and both have been incorporated into the automated manipulation, data acquisition and evaluation system. (orig.) [de

  3. Eddy current testing using digital technology

    International Nuclear Information System (INIS)

    Houseman, H.E.; Lamb, L.T.; Kitson, B.

    1985-01-01

    Eddy current inspection techniques have been used extensively in industry as an accepted method of non-destructive testing. The application of this technology has proven invaluable for both the control of product quality during the manufacturing process as well as the verification of material integrity throughout the life of a given component. One of the major areas in the power industry where eddy current techniques have been used is for the inspection of installed tubing in various heat exchangers including the steam generators of pressurized water reactor (PWR) nuclear steam supply systems. As increased emphasis is placed upon the operability and safety of these components, test instrumentation has been advanced to improve the efficiency and reliability of inservice inspections. At the same time, plant owners along with manufacturers and inspection service vendors are developing analytical tools for assessing the inspection results. One of the techniques that offers significant potential has been made possible by recent advances in digital technology. The application of digital techniques to the eddy current method offers not only a means to improve the test instrumentation but also an environment whereby other facets of the inservice inspection effort can be enchanced

  4. In-service behaviour of creep strength enhanced ferritic steels Grade 91 and Grade 92 – Part 2 weld issues

    International Nuclear Information System (INIS)

    Parker, Jonathan

    2014-01-01

    In Creep Strength Enhanced Ferritic steels control of both composition and heat treatment of the parent steel is necessary to avoid producing components which have properties below the minimum expected by applicable codes. The degree of tempering involved in manufacture will modify the material hardness. While under most conditions hardness is reduced by tempering, exceeding the AC 1 temperature can lead to an increase in hardness. In this heat treatment the properties will be relatively poor even though the measured hardness may be apparently acceptable. Thus, care should be exercised in imposing an acceptance test of components based on simple hardness alone. Differences in parent material heat treatment and composition apparently have remarkably little influence on the creep life of the heat affect zone (HAZ). Thus, Type IV cracking in the fine grained or intercritically heat treated regions of the HAZ does not appear to directly depend on the strength of the base steel. This form of in-service damage is relatively difficult to detect using traditional methods of non-destructive testing. Moreover, since repeated heat treatment leads to over tempering and a degradation of properties, specific procedures for making and then lifing repair welds are required. The present paper summarizes examples of damage and discusses best option repairs. -- Highlights: ► For many components damage in the weld heat affected zone will be the primary source of in-service problems. ► Repair approaches should consider the influence of heat flow on metallurgical transformations. ► Both development of residual stresses and the local properties of the constituent zones influence Type IV damage. ► Serviceability of components in the creep range must consider stress, temperature and applicable material properties

  5. Hegemonic Masculinity in Sport Education: Case Studies of Experienced In-Service Teachers with Teaching Orientations

    Science.gov (United States)

    Chen, YuChun; Curtner-Smith, Matthew

    2013-01-01

    Research has revealed that while pre-service teachers (PTs) with coaching orientations reinforce sexism and masculine bias, those with teaching orientations combat and reject it. The purpose of this study was to examine four sport education (SE) seasons taught by two experienced in-service teachers for the presence or absence of sexism and…

  6. Maintenance, surveillance and in-service inspection in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    Effective maintenance, surveillance and in-service inspection (MS and I) are essential for the safe operation of a nuclear power plant. The objective of this Safety Guide is to provide recommendations and guidance for MS and I activities to ensure that SSCs important to safety are available to perform their functions in accordance with the assumptions and intent of the design. This Safety Guide covers the organizational and procedural aspects of MS and I. However, it does not give detailed technical advice in relation to particular items of plant equipment, nor does it cover inspections made for and/or by the regulatory body. This Safety Guide provides recommendations and guidance for preventive and remedial measures, including testing, surveillance and in-service inspection, that are necessary to ensure that all plant structures, systems and components (SSCs) important to safety are capable of performing as intended. This Safety Guide covers measures for fulfilling the organizational and administrative requirements for: establishing and implementing schedules for preventive and predictive maintenance, repairing defective plant items, selecting and training personnel, providing related facilities and equipment, procuring stores and spare parts, and generating, collecting and retaining maintenance records for establishing and implementing an adequate feedback system for information on maintenance. MS and I should be subject to quality assurance in relation to all aspects important to safety. Quality assurance has been dealt with in detail in other IAEA safety standards and is covered here only in specific instances, for emphasis. In Section 2, a concept of MS and I is presented and the interrelationship between maintenance, surveillance and inspection is discussed. Section 3 concerns the functions and responsibilities of different organizations involved in MS and I activities. Section 4 provides recommendations and guidance on such organizational aspects as

  7. Maintenance, surveillance and in-service inspection in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    Effective maintenance, surveillance and in-service inspection (MS and I) are essential for the safe operation of a nuclear power plant. The objective of this Safety Guide is to provide recommendations and guidance for MS and I activities to ensure that SSCs important to safety are available to perform their functions in accordance with the assumptions and intent of the design. This Safety Guide covers the organizational and procedural aspects of MS and I. However, it does not give detailed technical advice in relation to particular items of plant equipment, nor does it cover inspections made for and/or by the regulatory body. This Safety Guide provides recommendations and guidance for preventive and remedial measures, including testing, surveillance and in-service inspection, that are necessary to ensure that all plant structures, systems and components (SSCs) important to safety are capable of performing as intended. This Safety Guide covers measures for fulfilling the organizational and administrative requirements for: establishing and implementing schedules for preventive and predictive maintenance, repairing defective plant items, selecting and training personnel, providing related facilities and equipment, procuring stores and spare parts, and generating, collecting and retaining maintenance records for establishing and implementing an adequate feedback system for information on maintenance. MS and I should be subject to quality assurance in relation to all aspects important to safety. Quality assurance has been dealt with in detail in other IAEA safety standards and is covered here only in specific instances, for emphasis. In Section 2, a concept of MS and I is presented and the interrelationship between maintenance, surveillance and inspection is discussed. Section 3 concerns the functions and responsibilities of different organizations involved in MS and I activities. Section 4 provides recommendations and guidance on such organizational aspects as

  8. Application of risk-informed methods to in-service piping inspection in Framatome type nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Jin Hoi; Lee, Jeong Seok; Yun, Eun Sub

    2014-01-01

    The Pressurized water reactor owners group (PWROG) developed and applied a risk-informed in-service inspection (RI-ISI) program, as an alternative to the existing ASME Section XI sampling inspection method. The RI-ISI programs enhance overall safety by focusing inspections of piping at high safety significance (HSS) locations where failure mechanisms are likely to be present. Additionally, the RI-ISI program can reduce nondestructive evaluation (NDE) exams, man-rem exposure for inspectors, and inspection time, among other benefits. The RI-ISI method of in-service piping inspection was applied to 3 units (KSNPs: Korea standard nuclear power plants) and is being deployed to the other units. In this paper, the results of RI-ISI for a Framatome type (France CPI) nuclear power plant are presented. It was concluded that application of RI-ISI to the plant could enhance and maintain plant safety, as well as provide the benefits of greater reliability.

  9. Examining the Effectiveness of the In-service Training Program for the Education of the Academically Gifted students in Turkey: A Case Study

    Directory of Open Access Journals (Sweden)

    Hasan Said TORTOP

    2014-12-01

    Full Text Available In this study, examining the effectiveness of in-service training for gifted education has been conducted. In the study, 30 Classroom, Science, Mathematics and Preschool teachers working at schools in different cities of Turkey, took part as volunteer participants. Moreover, some criteria were specified for determining the participants. In this in-service training, teachers have received theoretical and practical training in the academicians who study on gifted education. In this process, they have designed units in groups according to the Education Program for Gifted Student Bridge with University (EPGBU curriculum. The research has been designed as a case-study research which is one of the qualitative research models. In the study, some data tools (scales, interview form and the documents were utilized Two of data collection tools were developed by research. These were Science Fair Mentorship Self-efficacy Scale for Teachers (SFMSST and Gifted Education Self-efficacy Scale for Teachers (GESST. As a result of a one-week in-service training, it has been determined that the teachers’ perception of self-efficacy for scientific research mentorship and gifted education increased.

  10. Ultrasonic wall thickness gauging for ferritic steam generator tubing as an in-service inspection tool

    International Nuclear Information System (INIS)

    Haesen, W.M.J.; Tromp, Th.J.

    1980-01-01

    In-service inspection of LWR steam generators is more or less a standard routine operation. The situation can be very different for LMFBRs. For the SNR 300 (Kalkar Power Station) the situation is different because the steam generators have ferritic tubing. The tube walls are comparatively thick, 2 to 4.5 mm. During inservice examinations the steam generators will be drained on both sides, however on the sodium side a sodium film will be present. Furthermore the SNR 300 will have two types of steam generator. A straight tube design and a helical coil design will be used. Both types consist of a evaporator and superheater. The steam generators are of course not radioactive. It is obvious that in this case the eddy current (EC) technique is not an enviable inservice inspection tool. Basically EC is a surface flaw detection technique. Only the saturation magnetisation method will improve the EC technique sufficiently for ferritic material. However the 'in bore examination' with the saturation technique was, in case of the SNR 300 steam generator tubing, considered impossible since the inner diameters are fairly small. Furthermore sodium traces may influence the EC method. Although multifrequency methods can solve this problem, EC is not considered as a useful tool for examining ferritic tubing. Another method is to employ the 'stray flux' method which is under development with the TNO organization in Holland. The EC and stray flux method do have one drawback, these methods do not detect gradual changes in wall thickness. Ultrasonic examinations will be used in the SNR 300 as the main inspection tool for the steam generators. In this paper the reasons why ultrasonic examination was selected are explained. The results of the development work on this subject are discussed

  11. Determination of in-service needs of Turkish high school science teachers in Istanbul

    Science.gov (United States)

    Ogan, Feral

    The purposes of this study were to identify the in-service needs of high school science teachers in Istanbul, Turkey according to the subgroups such as school type and gender and determine the priority obstacles preventing these science teachers from attendance at in-service programs. Moreover, this study aimed to find the other greatest needs of high school science teachers that are not mentioned in the survey instrument. The data for this research was gathered by conducting a survey in Istanbul, Turkey in Fall 2001 and Spring 2002 Semesters. Turkish translation of the modified version of a science teacher's needs inventory, Science Teacher Inventory of Need (STIN), entitled STIN-2 was used as the survey instrument. The subjects consisted of 75 high school science teachers who were selected from 369 high schools by using stratified random sampling in grades nine through eleven. By personally administering the survey, 422 science teachers from 75 high schools completed the survey and a 97% response rate was achieved. The results obtained in this study show that Turkish high school science teachers in Istanbul have a number of shared needs. One other indication is that they also have a number of needs, which are specific to subgroups of those science teachers.

  12. Theory and Practice in In-Service Teacher Learning: Teachers' Reconceptualisation of Curriculum in History Lessons

    Science.gov (United States)

    Moyo, Nathan; Modiba, Maropeng

    2014-01-01

    This paper reports on the findings of a qualitative interpretive study that was undertaken to determine how in-service teachers at Great Zimbabwe University were able (or not) to translate a theory that they were exposed to into practice during history lessons. Drawing on a range of data, the study explored how the teachers, who were purposively…

  13. How In-Service Science Teachers Integrate History and Nature of Science in Elementary Science Courses

    Science.gov (United States)

    Hacieminoglu, Esme

    2014-01-01

    The purpose of this study is to investigate how the in-service science teachers' (IST) perceptions and practices about curriculum and integration of the history of science (HOS) and the nature of science (NOS) affect their science courses. For this aim, how ISTs integrated the NOS and HOS in their elementary science courses for understanding of…

  14. Study on practical application of risk informed inservice inspection

    International Nuclear Information System (INIS)

    Sato, Chikahiro; Machida, Hideo; Takeda, Shuhei; Miyata, Koichi; Nishino, Shoichiro

    2009-01-01

    This paper describes pilot study relevant to the application of risk informed inservice inspection (RI-ISI) to class 1 piping systems in a Japanese typical BWR5 plant. The benefits of making use of risk information are improvement in plant safety, quality of inspection and explanation of security activities in nuclear power plants. The current RI-ISI procedures and rules were developed to take advantage of lessons learned from PSA data and piping failure experiences, and are expected to rationalize of security activities for plant operation and maintenance. To introduce RI-ISI, it is necessary to collaborate with industry, academia and government. Development of the technical basis is one of the key issues to become practical of RI-ISI programs. (author)

  15. A Comparison of Centralized and Decentralized Inservice Education Programs: Teacher Involvement, Program Characteristics, and Job Satisfaction.

    Science.gov (United States)

    Perez, Roberto

    Inservice programs that are likely to accomplish their objectives are characterized by: (1) differentiated training experiences; (2) teachers in active roles; (3) an emphasis on demonstration, supervised trials, and feedback; (4) sharing and mutual assistance; (5) activities linked to a general effort of the school; (6) teachers who choose goals…

  16. SNAC: San Mateo Nutrition Activity Curriculum. "Swing Into Nutrition" (Staff In-Service Guide and Staff Workbook).

    Science.gov (United States)

    San Mateo City Elementary School District, CA.

    This inservice training guide on nutrition activities for preschool and elementary school teachers consists of 14 lesson plans for two workshops and more than 20 related instructional handouts that can be copied for teachers. The first workshop for teachers provides a rationale for nutrition education ine elementary curriculum as well as…

  17. Experience on implementing risk-oriented in-service inspection at NPP in USA

    International Nuclear Information System (INIS)

    Grebenyuk, Yu.P.; Zaritskij, N.S.; Kovyrshin, V.G.; Kostenko, S.P.

    2001-01-01

    Experience of implementing risk-oriented in-service inspection (RIISI) of pipelines at the US NPP analyzed. RIISI processes according to the methodologies developed by Westinghouse and EPRI are described and compared. The information is addressed concerning practical matters of RIISI implementing at NPP Beaver Valley and Arkansas Nuclear One. Regulatory activity of the US NRC while implementing NRC at the US NPP. It is shown that using RIISI at NPP is aimed at improvement of examination efficiency, decreasing costs and occupational dose loads while inspecting pipelines

  18. An international survey of in-service inspection experience with prestressed concrete pressure vessels and containments for nuclear reactors

    International Nuclear Information System (INIS)

    1982-04-01

    An international survey is presented of experience obtained from the in-service surveillance of prestressed concrete pressure vessels and containments for nuclear reactors. Some information on other prestressed concrete structures is also given. Experience has been gained during the working life of such structures in Western Europe and the USA over the years since 1967. For each country a summary is given of the nuclear programme, national standards and Codes of Practice, and the detailed in-service inspection programme. Reports are then given of the actual experience obtained from the inspection programme and the methods of measurement, examination and reporting employed in each country. A comprehensive bibliography of over 100 references is included. The appendices contain information on nuclear power stations which are operating, under construction or planned worldwide and which employ either prestressed concrete pressure vessels or containments. (U.K.)

  19. Round Robin Test for Performance Demonstration System of Ultrasound Examination Personnel in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Young Ho; Yang, Seung Han; Kim, Yong Sik; Yoon, Byung Sik; Lee, Hee Jong

    2005-01-01

    Ultrasound testing performance during in-service inspection for the main components of NPPs is strongly affected by each examination person. Therefore, ASME established a more strict qualification requirement in Sec. XI Appendix VIII for the ultrasound testing personnel in nuclear power plants. The Korean Performance Demonstration (KPD) System according to the ASME code for the ultrasonic testing personnel, equipments, and procedures to apply to the Class 1 and 2 piping ultrasound examination of nuclear power plants in Korea was established. And a round robin test was conducted in order to verify the effectiveness of PD method by comparing the examination results from the method of Performance Demonstration (PD) and a traditional ASME code dB-drop method. The round robin test shows that the reliability of the PD method is better than that of the dB-drop method. As a result, application of the PD method to the in-service inspection of the nuclear power plants will improve the performance of ultrasound testing

  20. PAT portable appliance testing : in-service inspection and testing of electrical equipment

    CERN Document Server

    Scaddan, Brian

    2015-01-01

    The Electricity at Work Regulations 1989 requires any electrical system to be constructed, maintained and used in such a manner as to prevent danger. This means that inspection and testing of systems, including portable appliances, is needed in order to determine if maintenance is required. This book explains in clear language what needs to be done and includes expert advice on legislation as well as actual testing. The book contains an appendix providing the electrical fundamentals needed by non-specialists and also has sample questions (with answers) for the C&G 2377 exam. It is also an ideal revision guide for the non-specialist, such as maintenance staff and caretakers who carry out these tasks part-time, alongside their many other duties.

  1. Update on Multiple Ovulations in Dairy Cattle.

    Science.gov (United States)

    Macmillan, Kira; Kastelic, John P; Colazo, Marcos G

    2018-04-24

    This review updates the causal mechanisms and risk factors for multiple ovulations (MOV) in cattle. Clearly, MOV can lead to twin pregnancies, which negatively affects the health, production, and reproduction of cows. Therefore, a better understanding of the factors causing MOV may help to reduce twinning. Multiple ovulations occur after two or more follicles deviate and achieve codominance. The MOV rate is influenced by a complex network of hormones. For example, MOV is more common during periods of low progesterone (P4), that is, in anovulatory cattle or when luteolysis coincides with the selection of the future ovulatory follicle. There is also strong evidence for the luteinizing hormone (LH) being the primary factor leading to codominance, as high P4 concentrations suppress the transient LH surges and can reduce the ovulation rate in cattle or even inhibit deviation. Rates of MOV are increased in older and higher-producing dairy cows. Increased milk production and dry matter intake (DMI) increases hormone clearance, including P4; however, the association between milk yield and MOV has not been consistent. Additional risk factors for MOV include ovarian cysts, diet, season, and genetics.

  2. Evaluation of flaw characteristics and their influence on inservice inspection reliability

    International Nuclear Information System (INIS)

    Becker, F.L.

    1980-01-01

    This report describes the results of the first year's effort of a five year program which is being conducted by Battelle, Pacific Northwest Laboratories, on behalf of the US Nuclear Regulatory Commission. This initial effort was directed toward identification and quantification of inspection uncertainties, which are likely to occur during inservice inspection of LWR primary piping systems, and their influence on inspection reliability. These experiments were conducted on 304 stainless steel samples, however, the results are equally applicable to other materials. Later portions of the program will extend these measurements and evaluations to other materials and conditions

  3. Knowledge and Beliefs about Developmental Dyslexia: A Comparison between Pre-Service and In-Service Peruvian Teachers

    Science.gov (United States)

    Echegaray-Bengoa, Joyce; Soriano-Ferrer, Manuel; Joshi, R. Malatesha

    2017-01-01

    The purpose of this study was to investigate the knowledge, misconceptions, and knowledge gaps of Peruvian pre-service teachers (PSTs) and in-service teachers (ISTs). To do so, 112 PSTs and 113 ISTs completed the Knowledge and Beliefs About Developmental Dyslexia Scale (KBDDS). Results show that ISTs scored significantly higher than PSTs.…

  4. Guided Portfolio Writing as a Scaffold for Reflective Learning in In-Service Contexts: A Case Study

    Science.gov (United States)

    Pires Pereira, Íris Susana; Cristo Parente, Maria Cristina; Vieira da Silva, Cristina

    2016-01-01

    Language is widely recognized as an inescapable mediating tool for professional learning, and with this text we want to contribute to a better understanding of the particular role that guided writing can play in in-service professional reflective learning. We analysed one pre-school teacher's written portfolio, the construction of which was guided…

  5. Comparison between Synchronous and Asynchronous Instructional Delivery Method of Training Programme on In-Service Physical Educators' Knowledge

    Science.gov (United States)

    Emmanouilidou, Kyriaki; Derri, Vassiliki; Antoniou, Panagiotis; Kyrgiridis, Pavlos

    2012-01-01

    The purpose of the study was to compare the influences of a training programme's instructional delivery method (synchronous and asynchronous) on Greek in-service physical educators' cognitive understanding on student assessment. Forty nine participants were randomly divided into synchronous, asynchronous, and control group. The experimental groups…

  6. Success in Implementation of a Resident In-Service Examination Review Series

    Science.gov (United States)

    Forcucci, Jessica A.; Hyer, J. Madison; Bruner, Evelyn T.; Lewin, David N.; Batalis, Nicholas I.

    2017-01-01

    Abstract Objectives: Primary pathology board certification has been correlated with senior resident in-service examination (RISE) performance. We describe our success with an annual, month-long review series. Methods: Aggregate program RISE performance data were gathered for 3 years prior to and 3 years following initiation of the review series. In addition, mean United States Medical Licensing Examination Step 1 and 2 Clinical Knowledge scores for residents participating in each RISE examination were obtained to control for incoming knowledge and test-taking ability. Linear models were used to evaluate differences in average RISE performance prior to and following the initiation of the review series in addition to controlling for relevant covariates. Results: Significant improvement was noted in the grand total, anatomic pathology section average, clinical pathology section average, and transfusion medicine section. Although not statistically significant, improvement was noted on the cytopathology and clinical chemistry sections. There was no significant difference in scores in hematopathology, molecular pathology, and the special topics section average. In addition, improvement in primary pathology board certification rates was also noted. Conclusions: Institution of a month-long RISE review series demonstrated improved overall performance within our training program. The success could easily be replicated in any training program without significant disruption to an annual didactic series. PMID:28340222

  7. La Capacitacion de Docentes Como Prioridad de los Sistemas Educativos de America Latino y al Caribe (In-Service Teacher Training as a Priority of Latin American and Caribbean Educational Systems).

    Science.gov (United States)

    Valle, Victor M.

    Whenever top-level officials in Latin American and Caribbean educational systems are approached, the topic of inservice teacher training is presented as a major priority. This paper outlines some ideas about the subject of inservice teacher training as a priority of educational systems in Latin American and Caribbean countries. The most frequent…

  8. Routine testing on protective and safety systems and components

    International Nuclear Information System (INIS)

    Rysy, W.

    1977-01-01

    1) In-process inspection, tests during commissioning. 2) Tests during reactor operation. 2.1) Reactor protection system, for example: continuous auto-testing by a dynamic system, check of the output signals; 2.2) safety features: selected examples: functional tests on the ECCS, trial operation of the emergency diesels. 3) Tests during refuelling phase. 3.1) Containment: Leakage rate tests, leak testing; 3.2) coolant system: selected examples: inservice inspections of the pressure vessel, eddy current testing of the steam generator, functional tests of safety valves. (orig./HP) [de

  9. Acoustic emission testing of piston check valves

    International Nuclear Information System (INIS)

    Stewart, D.L.

    1994-01-01

    Based on test experience at Comanche Peak Unit 1, an acoustic emission data evaluation matrix for piston check valves has been developed. The degradations represented in this matrix were selected based on Edwards piston check valve failure data reported in the Nuclear Plant Reliability Data System. Evidence to support this matrix was collected from site test data on a variety of valve types. Although still under refinement, the matrix provides three major attributes for closure verification, which have proven useful in developing test procedures for inservice testing and preventing unnecessary disassembly

  10. Fracture toughness assessment of in-service aged primary circuit elbows using mini C(T) specimens taken from outer skin

    International Nuclear Information System (INIS)

    Jayet-Gendrot, S.; Meylogan, T.; Ould, P.

    1995-05-01

    Type CF8M cast duplex stainless steels used in the primary circuit elbows of pressurized water reactors are subject to thermal aging embrittlement at their service temperature, around 300 deg. C. This phenomenon affects their fracture toughness properties. In order to assess the residual fracture toughness of these elbows, estimations are made through predictive formulae based on chemical composition and aging conditions, which provide safe values. However, in the case of the most sensitive materials, it is important to obtain more accurate estimations. A new method of determination was thus considered, based on the testing of mini-CT specimens taken from the skin of in-service elbows. The feasibility of using mini-CT specimens to evaluate the tearing resistance of cast duplex stainless steels seems at first sight difficult, in particular because of the very coarse metallurgical structure of these steels: will small specimens be representative of larger volumes (mainly regular T-CT specimens) and will they not induce too much scatter ? In order to answer such questions, an experimental validation program has been undertaken: the completed program shows that the method is relevant and leads to proposed guidelines which aim at optimizing the experimental results analysis. Then the method is applied to an in-service elbow: the results obtained are found to be in good agreement with the toughness estimations given by our predictive formulae. This subsequently contributes to the validation of the general methodology used for the justification of French primary circuit elbows. (authors). 7 refs., 4 figs., 5 tabs

  11. Learning the Discourse of Quality Assurance: A Case of Workplace Learning in Online In-Service Training

    Science.gov (United States)

    Lundin, Mona; Lundin, Johan

    2016-01-01

    Purpose: In this study, online in-service training for people employed in the food production industry is scrutinized. The purpose of this study is to analyse how the participants adapt to such online environments in terms of the kind of discussions they establish. The more specific interest relates to how the participants discuss current work…

  12. Developing Teacher Expertise at Work: In-Service Trainee Teachers in Colleges of Further Education in England

    Science.gov (United States)

    Lucas, Norman; Unwin, Lorna

    2009-01-01

    This paper presents findings from a study of the experiences of in-service trainee teachers in colleges of further education in England on programmes run under the auspices of and through franchise arrangements with universities. It argues that there is a significant gap between the rhetoric of gaining teaching qualifications through a work-based…

  13. Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Session 1A--Session 2C: Volume 1

    International Nuclear Information System (INIS)

    1994-07-01

    The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. This document, Volume 1, covers sessions 1A through session 2C. The individual papers have been cataloged separately

  14. Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Session 1A--Session 2C: Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. This document, Volume 1, covers sessions 1A through session 2C. The individual papers have been cataloged separately.

  15. Measurements for testing of fluoroscopic screens, including the photofluorographic units

    International Nuclear Information System (INIS)

    Balfanz, R.

    1986-01-01

    Image quality control measurements for fluoroscopic screens and photofluorographs have shown that both types of equipment have a long operating life, so that constancy and technical performance tests are absolutely necessary. It is recommended to conclude in-service maintenance contracts with the manufacturers. (DG) [de

  16. Development of non-destructive testing

    International Nuclear Information System (INIS)

    Park, D.Y.; Moon, Y.S.; Lim, B.K.

    1980-01-01

    Various standard test samples were made for eddy current test last year ('78) and several probes of eddy current test were fabricated this year ('79). The result of some basic experiments using these probes is described in this report. A EM 3300 Multitester (made by Automation Industries, U.S.A.) was purchased, which is the fundamental instrument for the examinations of steam generator U-tubes of nuclear power plant. After some necessary experiments had been performed with this instrument, we have participated in the first inservice inspection of KORI-1 nuclear power plant (Nov., '79) and accumulated much technical experiences. Some of its test results are described in this report. (author)

  17. Development of in-service meter testing (ISMET); Developpement de test de compteurs en service

    Energy Technology Data Exchange (ETDEWEB)

    Ullathorne, D. [BG Technology Ltd. (United Kingdom); Finnerty, G. [BG Transco plc. (United Kingdom)

    2000-07-01

    Managing a population of 19 million meters in the UK is a massive task for Transco, the UK's principal regulated gas transporter. Adopting a cost-effective approach to all aspects of mater work is crucial in today's regulated business environment. It was from a critical review of mater work processes that a need was identified for new test equipment to reinforce the introduction of a mater re-use policy. This would reduce mater transportation and refurbishment costs. BG Technology and Transco have jointly developed some low cost equipment suitable for testing residential gas meters used by Transco's Competent Person (TCP) workforce or by trained local depot operatives. The test equipment can determine whether the meter meets the national requirements for registration performance and hence can be re-used without refurbishment at central workshops. The equipment has been shown to be technically feasible in the laboratory. Field testing has allowed rapid development of working prototypes and provided a basis for conducting simple inter-rig comparison to verify the acceptability of the test method. The pilot trial has shown that the project objectives have been met, in providing low cost test equipment for widespread use by properly trained personnel. (authors)

  18. Changes in Default Alarm Settings and Standard In-Service are Insufficient to Improve Alarm Fatigue in an Intensive Care Unit: A Pilot Project.

    Science.gov (United States)

    Sowan, Azizeh Khaled; Gomez, Tiffany Michelle; Tarriela, Albert Fajardo; Reed, Charles Calhoun; Paper, Bruce Michael

    2016-01-11

    alarm parameters and frequency of replacing patients' electrodes. Despite the in-service, 50% (12/24) of the nurses specified their need for more training on cardiac monitors in the postproject period. Changing default alarm settings and standard in-service education on cardiac monitor use are insufficient to improve alarm systems safety. Alarm management in ICUs is very complex, involving alarm management practices by clinicians, availability of unit policies and procedures, unit layout, complexity and usability of monitoring devices, and adequacy of training on system use. The complexity of the newer monitoring systems requires urgent usability testing and multidimensional interventions to improve alarm systems safety and to attain the Joint Commission National Patient Safety Goal on alarm systems safety in critical care units.

  19. Novice-Service Language Teacher Development: Bridging the Gap between Preservice and In-Service Education and Development

    Science.gov (United States)

    Farrell, Thomas S. C.

    2012-01-01

    One reason for teacher attrition is that a gap exists between pre-service teacher preparation and in-service teacher development, in that most novice teachers suddenly have no further contact with their teacher educators, and from the very first day on the job, must face the same challenges as their more experienced colleagues, often without much…

  20. Pre-Service and In-Service Teachers' Experiences of Learning to Program in an Object-Oriented Language

    Science.gov (United States)

    Govender, I.; Grayson, D. J.

    2008-01-01

    This paper presents the results of an investigation into the various ways in which pre-service and in-service teachers experience learning to program in an object-oriented language. Both groups of teachers were enrolled in university courses. In most cases, the pre-service teachers were learning to program for the first time, while the in-service…